秋穗正

期刊论文

1. 章静，王明军，田文喜，巫英伟，苏光辉，秋穗正（2026）. 核动力系统热工安全分析的智能优化与评价技术. 《科学通报》.
2. 巫英伟，章静，贺亚男，田文喜，苏光辉，秋穗正（2026）. 先进核燃料元件性能堆外验证及服役评价技术研究. 《科学通报》.
3. 余鑫，王恒，高文祥，郭凯伦，张泽秦，秋穗正（2026）. 基于时序深度学习模型的高温热管启动过程预测方法研究. 《热能动力工程》.DOI
4. 吴世浩，吴晓程，张亚培，王栋，马鹏飞，田文喜，秋穗正，苏光辉（2026）. 高温蒸汽氛围下Cr涂层Zr合金包壳共晶熔化及氧化特性研究. 《中国核工业教育学会第三届学术年会》.
5. 方嘉辉，国文慧，高新力，章静，王明军，巫英伟，田文喜，苏光辉，秋穗正（2026）. 基于贝叶斯神经网络的冷却剂丧失事故不确定性预测方法. 《哈尔滨工程大学学报》.
6. 王一家，马文慧，徐乐，章静，王明军，巫英伟，田文喜，苏光辉，秋穗正（2026）. 小样本下基于Transformer与树模型的临界热流密度预测及误差行为分析. 《哈尔滨工程大学学报》.
7. 姜铭雨，黄擎宇，章静，王明军，巫英伟，田文喜，苏光辉，秋穗正（2026）. 基于非支配排序遗传算法的系统分析程序优化技术. 《哈尔滨工程大学学报》.
8. 周星光，张大林，李新宇，余红星，田文喜，秋穗正，苏光辉（2026）. 液态金属非稳定分层混合对流的湍流输运研究. 《力学学报》.
9. 李亮国，龙彪，刘继墉，卢冬华，苏前华，巫英伟，秋穗正，苏光辉（2026）. 反应堆压力容器下降段吹扫现象试验研究及数值分析. 《原子能科学技术》.
10. 李永康，吴世浩，张亚培，武俊梅，田文喜，苏光辉，秋穗正（2026）. 安全壳严重事故分析软件CAP开发与验证. 《原子能科学技术》.
11. 李亮国，余健明，刘继墉，卢冬华，邢军，巫英伟，秋穗正，苏光辉，田文喜（2026）. 小型堆二次侧非能动余排系统运行特性研究. 《核安全》.DOI
12. 武文强，张大林，黄涛，冯振宇，杜鹏，田文喜，秋穗正，苏光辉（2026）. 基于有限体积求解平台的核反应堆系统分析求解器开发. 《核动力工程》.DOI
13. 黑梓豪，张嘉睿，王成龙，郭凯伦，秋穗正（2026）. 充液量对高温碱金属热管竖直传热性能影响实验研究. 《核科学与工程》.DOI
14. 陈楠，贺亚男，章静，巫英伟，周毅，田文喜，秋穗正（2026）. 快堆UO2燃料与HT9包壳化学相互作用数值模拟研究. 《原子能科学技术》.
15. 李亮国，龙彪，刘继墉，卢冬华，苏前华，巫英伟，秋穗正，苏光辉（2026）. 压力容器下降段CCFL现象试验研究及数值分析. 《原子能科学技术》.
16. 贠世昌，李新宇，张大林，宋苹，田文喜，秋穗正，苏光辉（2026）. 一体化小型氟盐冷却高温堆系统稳态运行方案设计. 《核动力工程》.
17. 李长忠，李卓凡，仇子铖，王成龙，秋穗正（2026）. 氦氙混合气体在矩形窄缝通道内流动传热特性数值研究. 《原子能科学技术》.
18. 陈晓晴，李新宇，张大林，冯振宇，乔鹏瑞，肖常志，田文喜，苏光辉，秋穗正（2026）. 温度对超临界CO2射流铅铋空间的影响机制研究. 《工程热物理学报》.
19. 焦昊宇，冯振宇，张大林，肖常志，牛志新，田文喜，秋穗正，苏光辉（2026）. 铅冷快堆蒸汽发生器传热管破裂事故下的气泡迁移特性研究. 《核动力工程》.
20. 金钊，刘硕，王成龙，田文喜，苏光辉，秋穗正（2026）. 空间锂冷堆冷却介质熔化凝固特性研究. 《原子能科学技术》.
21. 卢国庆，肖千喜，陈荣华，田文喜，秋穗正（2026）. 基于可视化交互式核动力系统瞬态分析程序的先进压水堆蒸汽发生器传热管破裂事故. 《哈尔滨工程大学学报》.
22. 张泽秦，徐东东，张恺，王成龙，郭凯伦，田文喜，秋穗正（2026）. 基于热动电全耦合分析的自由活塞斯特林发电机三阶动态模型研究. 《核技术》.
23. Shihao Wu, Haotian Lu, Yapei Zhang, Jian Yu, Wenxi Tian, Suizheng Qiu, G.H. Su (2026). Study on the reflooding behavior of debris bed based on the thermal non-equilibrium porous media model. Progress in Nuclear Energy.DOI
24. Xingguang Zhou, Dalin Zhang, Xinyu Li, Wentao Ma, Hongxing Yu, Wenxi Tian, Suizheng Qiu, Guanghui Su (2026). Flow organization in unstably stratified mixed convection at Ri = 1 for heavy liquid metals. Physical Review Fluids.DOI
25. Yiheng Fei, C H Wang, Wenxi Tian, Suizheng Qiu (2026). Coherent thermal radiation heat transfer of Micron-sized satellite droplet flow in space droplet radiators. Applied Thermal Engineering.DOI
26. Yijia Wang, Jing Zhang, Mingjun Wang, Wenxi Tian, G.H. Su, Suizheng Qiu (2026). Unit-aware physical embedding transformer for critical heat flux prediction and extrapolation at boiling crisis boundaries. Energy.DOI
27. X F Yu, Wenxiang Gao, Kailun Guo, Z ZHANG, Heng Wang, Mingjun Wang, Suizheng Qiu, Wenxi Tian (2026). Fourier neural operator-based approach for real-time prediction of high-temperature heat pipes frozen startup. Applied Thermal Engineering.DOI
28. Lanfei Yuan, Ziang Li, Rongshuan Xu, C Wang, Wenxi Tian, Suizheng Qiu (2026). Mechanistic analysis of solidification-induced flow blockage and thermohydraulic deterioration in forced convection systems. International Communications in Heat and Mass Transfer.DOI
29. Yin Zhang, Zeqin Zhang, Chenglong Wang, Kailun Guo, Wenxi Tian, Guanghui Su, Suizheng Qiu (2026). Geometric design optimization and application of three-stage segmented thermoelectric generators in heat pipe reactor. Applied Thermal Engineering.DOI
30. Tianrui Li, Xinkun Xiao, Shuai Wang, R G Chen, Wenxi Tian, Suizheng Qiu (2026). AM‐GMSIS: An Efficient Reliability Evaluation Method for Passive Nuclear Safety Systems Based on Ensemble Neural Network and Adaptive Multimodal Sampling. Risk Analysis.DOI
31. Chunxiao Yu, Weiwei Li, Zhiwen Dai, Chenglong Wang, Suizheng Qiu, Wenxi Tian (2026). Numerical investigation of particle blockage mechanisms in throttle devices based on CFD-DEM coupling. Progress in Nuclear Energy.DOI
32. Wen Zhibo, Li Xinyu, D H Zhang, Qiao Pengrui, Wenxi Tian, Suizheng Qiu, Su Guanghui (2026). Theoretical and numerical study on discontinuous Galerkin flux reconstruction method in thermal-hydraulic analysis. Annals of Nuclear Energy.DOI
33. Ruiyu Han, Shaopeng He, Ruijie Wang, Zili Gong, Mingjun Wang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2026). Numerical study of flow-induced vibration in heat transfer tubes of shell-and-tube heat exchangers under ocean conditions. Progress in Nuclear Energy.DOI
34. Wen Ding, R. H. Chen, Qifan Yu, Chenglong Wang, Wenxi Tian, Suizheng Qiu (2026). Experimental investigation on thermal-hydraulic interaction between subcooled water and high-temperature lead‑bismuth eutectic under steam generator tube rupture accident. Applied Thermal Engineering.DOI
35. Changzhong Li, Zhuofan Li, Chenglong Wang, Dahuan Zhu, Wenxi Tian, G.H. Su, Suizheng Qiu (2026). Forced convection heat transfer and thermal stratification of helium-xenon mixtures along close-packed rod arrays. International Journal of Heat and Mass Transfer.DOI
36. Haoyang Li, D. J. Zhang, Xinyu Li, Boyang Jiang, Xiaoyan Yang, Pengrui Qiao, Wenxi Tian, Suizheng Qiu, G.H. Su (2026). Transient and mechanical analysis of phenomena of supercritical carbon dioxide jet into lead-bismuth eutectic in lead-cooled fast reactor. Progress in Nuclear Energy.DOI
37. Jiarui Zhang, Yuankun Mou, Kailun Guo, Zihao Hei, Chenglong Wang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2026). Investigation of heat transfer behavior of high-temperature heat pipes under transient input power conditions. Applied Thermal Engineering.DOI
38. Liaojie Deng, Dalin Zhang, Xinyu Li, Yuehua Chen, Lei Zhou, Wenxi Tian, Suizheng Qiu, Guanghui Su (2026). Development of delayed neutron precursor and decay heat models for molten salt reactors using runge–kutta discontinuous Galerkin methods. Applied Thermal Engineering.DOI
39. Shuo Liu, Wenshu Li, Chenglong Wang, Dalin Zhang, Pengrui Qiao, Suizheng Qiu (2026). Calibration and inversion using a data-model fusion-driven method with application to lead‑bismuth cooled reactors. Applied Thermal Engineering.DOI
40. Huifang Zhang, Jian Yu, Yapei Zhang, Shihao Wu, Wenxi Tian, Suizheng Qiu, Guanghui Su (2026). Study on hydrodynamic characteristics of symmetric two-droplet impact on film using lattice Boltzmann method. Progress in Nuclear Energy.DOI
41. Yupeng Yang, Scolaro Alessandro, Fiorina Carlo, Giovanni Nervi, Chenglong Wang, Yuan Zhou, Yuan Yuan, Suizheng Qiu (2026). An approach for numerical investigation of 3D lead‑bismuth helical coiled once-through steam generator based on GeN-Foam solver. International Communications in Heat and Mass Transfer.DOI
42. Dongdong Xu, Jiren Li, Panxiao Li, Chenglong Wang, Wenxi Tian, Suizheng Qiu, GH Su (2026). Experimental study on the operating characteristics of high-temperature heat Pipe–Stirling thermoelectric conversion systems. Energy.DOI
43. K Zhang, Zhao Jin, Dongdong Xu, Yihao Yang, Chenglong Wang, Xuesong Wang, Wenxi Tian, Anran Zheng, Suizheng Qiu, G. H. Su (2026). Surrogate-assisted dynamic response prediction and intelligent fault management for gas–cooled reactor–Brayton energy systems. Applied Thermal Engineering.DOI
44. Binzhuo Xia, Di Liu, Kui Zhang, JinQuan YAN, Zhan Liu, Fanting Xia, R. H. Chen, Fujun Gan, Wenxi Tian, Bo Yang, Suizheng Qiu (2026). Experimental study on CHF with low mass flux in a full-scale rod based on the heated perimeter equivalent method. Progress in Nuclear Energy.DOI
45. Shihao Wu, Xingyu Wang, Yapei Zhang, Yicong Lan, Wenxi Tian, Suizheng Qiu, GH Su (2026). Study on the melting and relocation behavior of dispersion helical cruciform fuel under accidents. Progress in Nuclear Energy.DOI
46. Q. Zhang, N Chen, Shiqi Wang, Mengdi Wang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2026). Numerical Study of Aerosol Deposition in Micro-channel Based on Openfoam. Springer proceedings in physics.DOI
47. W. Ding, X. K. Xiao, R. H. Chen, W. X. Tian, Suizheng Qiu (2026). Numerical Investigation of Debris Bed Formation and Coolability Based on the Optimized MPS-DEM Method. Springer proceedings in physics.DOI
48. Jie Rong, Mengdi Wang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2026). Study on the Trajectory of Foreign Objects on the Secondary Side of Nuclear Power Steam Generator. Springer proceedings in physics.DOI
49. Y. Wang, HaoLi Wang, Shihao Wu, Yapei Zhang, Wenxi Tian, Suizheng Qiu, G. H. Su (2026). Study on the Impact of Squib Valve Opening Time on Maximum Temperature of Cladding During a SBO Accident in the ACP100. Springer proceedings in physics.DOI
50. HaoLi Wang, Yapei Zhang, Shihao Wu, Wenxi Tian, Suizheng Qiu, G. H. Su (2026). Numerical Analysis of Interface Stability During Molten Zirconium Oxidative Solidification. Springer proceedings in physics.DOI
51. Zhenyu Feng, Dalin Zhang, Wenqiang Wu, Lei Zhou, Wenxi Tian, Suizheng Qiu, G.H. Su (2026). Development of a 3D Thermal–Hydraulic Analysis Code for Aqueous Homogeneous Reactor Based on GeN-Foam. Springer proceedings in physics.DOI
52. Weifeng Wu, Dalin Zhang, X. Zhou, W. X. Tian, Suizheng Qiu, G. H. Su (2026). Study on Neutronic and Thermal–Hydraulic Coupling of a Molten Salt Reactor Based on GeN-FOAM. Springer proceedings in physics.DOI
53. S Wang, Mingjun Wang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2026). Characterization of Bubble Motion in Bottom Submerged Orifice Under Rolling Conditions. Springer proceedings in physics.DOI
54. Haoyang Li, Dalin Zhang, Wenxi Tian, Suizheng Qiu (2026). CFD Code Validation on NACIE-UP Rod Bundle: Review on Numerical Methods and Results. Springer proceedings in physics.DOI
55. Junfeng Liu, C. Wang, Wenshu Li, Xiaolong Ma, Suizheng Qiu (2026). Analysis of Thermal Hydraulic Coupling Stress Characteristics of Spiral Tube Steam Generator in High Temperature Gas Cooled Reactor. Springer proceedings in physics.DOI
56. Qianxi Xiao, Dezhi Wan, Ronghua Chen, Liqun Zhang, Si Ni, Wenxi Tian, Suizheng Qiu (2026). Research on Distributed Coupled Computational Methods Based on the Vitars Platform. Springer proceedings in physics.DOI
57. Ze Li, Fengtao Zhang, Jing Zhang, Yingwei Wu, Yanan He, Wenxi Tian, Suizheng Qiu, Guanghui Sui (2026). Experimental and Computational Analysis of Foreign Particle Transport in Pressurized Water Reactor Fuel Rod Bundles. Springer proceedings in physics.DOI
58. Xinhang Peng, Tian Zhang, Dalin Zhang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2026). MYRRHA Fast Reactor Am-Bearing Fuel Pins Modelling Using OFFBEAT. Springer proceedings in physics.DOI
59. 庞墨涵，郭硕，张大林，苏光辉，秋穗正，田文喜（2025）. 面向AI算力供电的小型氟盐冷却高温堆(FuSTAR)储热调峰研究. 《中国核科学技术进展报告（第九卷）中国核学会2025年学术年会论文集 第4册》.
60. 唐松胜，郭凯伦，田诗雨，孙奇士，王明军，张大林，王成龙，马誉高，田文喜，秋穗正（2025）. 高温热管丝网吸液芯上碱金属钠润湿特性研究. 《原子能科学技术》.
61. 张嘉睿，牟元坤，郭凯伦，王成龙，田文喜，秋穗正，苏光辉（2025）. 高温热管丝网式吸液芯考虑间隙影响的模型改进. 《原子能科学技术》.
62. 孔德祥，马翊超，章静，王明军，巫英伟，贺亚男，郭凯伦，田文喜，苏光辉，秋穗正（2025）. 基于物理信息机器学习算法的核反应堆换热系数预测. 《核技术》.
63. 闫星辰，刘奚彤，王明军，董正阳，陈冲，田文喜，秋穗正，苏光辉（2025）. 基于OpenFOAM的铅铋快堆堆芯-腔室一体化耦合计算方法研究. 《核动力工程》.DOI
64. 马翊超，孔德祥，田文喜，章静，巫英伟，秋穗正，苏光辉（2025）. 基于人工神经网络的堆芯两相流型预测模型开发. 《核动力工程》.DOI
65. 张睿潇，贺亚男，章静，巫英伟，田文喜，秋穗正，苏光辉（2025）. 铅铋合金填充间隙的SiC复合包壳燃料棒初步设计. 《核技术》.
66. 韩梓超，郭凯伦，王明军，章静，冯唐涛，田文喜，秋穗正（2025）. 压水堆核电厂温差发电模块热电特性耦合分析. 《核技术》.
67. 丁育哲，李伟，任全耀，李垣明，纪谢天，田文喜，章静，巫英伟，贺亚男，王明军，苏光辉，秋穗正（2025）. 多跨弹性支撑燃料棒振动特性分析方法. 《核技术》.
68. 吕鑫狄，张大林，李新宇，梁禹，邓坚，秋穗正，苏光辉（2025）. 小型氟盐冷却高温堆负荷跟踪运行能力分析. 《核技术》.
69. 刘硕，李文姝，金钊，王成龙，张大林，秋穗正（2025）. 液态锂在棒束通道中流动换热数值模拟研究. 《核技术》.
70. 王博，郭硕，张大林，田文喜，秋穗正，苏光辉（2025）. 钠冷快堆蒸汽发生器钠侧入口流量分配特性研究. 《核技术》.
71. 纪谢天，郭宏建，章静，巫英伟，贺亚男，王明军，苏光辉，秋穗正，田文喜（2025）. 基于大涡模拟的铅铋堆7棒束绕丝燃料流致振动特性分析. 《核技术》.
72. 张凌义，田文喜，杨勇，吕玉凤，苏光辉，秋穗正（2025）. 钠冷快堆自然循环试验模化分析研究. 《核科学与工程》.DOI
73. 陈青山，王明军，田文喜，秋穗正，苏光辉（2025）. 基于DPM-to-VOF方法的液滴射流撞壁过程研究. 《核动力工程》.DOI
74. 冯振宇，刘雅鹏，王博，张大林，李新宇，田文喜，秋穗正，苏光辉（2025）. 钠-水直流蒸汽发生器径向热工水力特性研究. 《核动力工程》.DOI
75. 蓝毅聪，张亚培，王兴宇，黎阳，宫厚军，田文喜，苏光辉，秋穗正（2025）. 基于粒子法的新型堆芯捕集器关键现象数值模拟研究. 《核动力工程》.DOI
76. 章静，王明军，田文喜，苏光辉，秋穗正（2025）. 人工智能算法在核反应堆热工水力预测分析中的初步探索. 《核动力工程》.DOI
77. 余剑，张亚培，苏光辉，田文喜，秋穗正（2025）. 基于可视化实验的双层熔融池传热及分层界面硬壳特性研究. 《核动力工程》.DOI
78. 苏光辉，董正阳，刘凯，王明军，田文喜，秋穗正（2025）. 核反应堆堆芯三维跨尺度多物理场耦合分析程序CorTAF开发进展. 《核动力工程》.DOI
79. 张丰弢，章静，巫英伟，贺亚男，田文喜，秋穗正（2025）. 基于CFD-DEM方法的安全壳碎片迁移流固耦合数值模拟研究. 《原子能科学技术》.
80. 王浩理，张亚培，田文喜，秋穗正，苏光辉（2025）. 熔融锆合金氧化凝固过程中微观结构演变过程模拟研究. 《原子能科学技术》.
81. 廖瑞安，王学松，祁琳，张大林，田文喜，苏光辉，秋穗正（2025）. TOPAZ-Ⅱ反应堆堆芯的稳态热工代理模型. 《核动力工程》.DOI
82. 陈青山，王明军，田野，郭凯伦，田文喜，秋穗正，苏光辉（2025）. 液滴撞击自由液面过程的数值模拟研究. 《核动力工程》.DOI
83. 叶伊博，何少鹏，王明军，田文喜，秋穗正，苏光辉（2025）. 基于深度学习的蒸汽发生器三维稳态温度场快速预测研究. 《核动力工程》.DOI
84. 黄金露，王成龙，刘天才，郭春秋，田文喜，苏光辉，秋穗正（2025）. 空间热环境对空间反应堆电源系统SP-100正常运行的影响. 《原子能科学技术》.
85. 马鹏飞，刘艳，曹留烜，张亚培，李修锐，田文喜，秋穗正，苏光辉（2025）. 原位TEM双离子束辐照钨的位错环演化研究. 《原子能科学技术》.
86. 国文慧，姜铭雨，章静，王明军，巫英伟，贺亚男，郭凯伦，田文喜，苏光辉，秋穗正（2025）. 基于动态时间规整的子通道程序数据同化技术研究. 《原子能科学技术》.
87. 何少鹏，王明军，田文喜，秋穗正，苏光辉（2025）. 非能动余热排出换热器流量分配及瞬态热分层特性数值模拟研究. 《原子能科学技术》.
88. 夏斌卓，夏凡莛，张魁，陈荣华，田文喜，秋穗正（2025）. 运动条件下的圆管临界热流密度试验及数值模拟研究. 《原子能科学技术》.
89. 张衍，王博，王成龙，张大林，杨洋，郭正荣，田文喜，秋穗正，苏光辉（2025）. 粗糙管内液态铅铋合金传热特性研究. 《原子能科学技术》.
90. 徐东东，李潘潇，王成龙，田文喜，秋穗正，苏光辉（2025）. 小型双端对置斯特林热电转换装置运行特性研究. 《原子能科学技术》.
91. 张智鹏，李潘潇，张泽秦，王成龙，郭凯伦，田文喜，苏光辉，秋穗正（2025）. 兆瓦级紧凑型热管堆堆芯设计方案研究. 《原子能科学技术》.
92. Jing Zhang, Mingjun Wang, Wenxi Tian, Yingwei Wu, Guanghui Su, Suizheng Qiu (2025). Intelligent optimization and evaluation techniques for thermal-hydraulic safety analysis of nuclear power systems. Chinese Science Bulletin (Chinese Version).DOI
93. H.-C. Zhang, Yapei Zhang, Shihao Wu, Wenxi Tian, Suizheng Qiu, Guanghui Su (2025). Highly accurate and interpretable machine learning models for predicting HTC in the presence of NCG on outer vertical tubes. Progress in Nuclear Energy.DOI
94. Haoli Wang, Simin Luo, Xinhai Zhao, Yapei Zhang, Yicong Lan, Yujian Wang, Shihao Wu, Dayan Ma, Junkai Deng, Wenxi Tian, Suizheng Qiu, G.H. Su (2025). Microstructure evolution of molten zirconium oxidative solidification: Experiment and numerical simulation. Materials & Design.DOI
95. Zhuofan Li, Changzhong Li, Chenglong Wang, Yanyu Sun, Dingsheng S. Wang, Wenxi Tian, Guanghui Su, Suizheng Qiu (2025). Experimental investigation of heat transfer and friction characteristics of high-pressure helium with variable properties in circular tubes. International Journal of Thermal Sciences.DOI
96. Yichao Ma, Dexiang Kong, Jing Zhang, Mingjun Wang, Wenxi Tian, Yingwei Wu, G.H. Su, Suizheng Qiu (2025). Safety characteristic analysis driven by machine learning algorithm for an offshore nuclear energy system. Progress in Nuclear Energy.DOI
97. Qingshan Chen, Qinrui Zhang, Cong Wang, Kailun Guo, Mingjun Wang, Xiaoyan Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2025). Numerical study of spray cooling: The effect of nozzle arrangement on heat transfer performance. International Journal of Multiphase Flow.DOI
98. Shuo Liu, Wenshu Li, Zhao Xin Jin, Chenglong Wang, Suizheng Qiu, Tai Shi, Mengyao He, Yinbo Yan (2025). Transient thermal–hydraulic characteristics of the lithium loop in space lithium-cooled fast reactor. Nuclear Engineering and Design.DOI
99. Hongquan Liu, Chuan Jing Lu, Yingwei Wu, Fengrui Xiang, Yanan He, Jing Zhang, Suizheng Qiu (2025). Design parameters sensitivity analysis of dispersed plate-type nuclear fuel in Reactivity Insertion Accident. Nuclear Engineering and Design.DOI
100. Lifan Zhao, Mingjun Wang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2025). Numerical Simulation of Foreign Object Motion on Secondary Side of Steam Generator Tube Zone. Springer proceedings in physics.DOI
101. Yicong Lan, Shihao Wu, Yapei Zhang, Xingyu Wang, Wenxi Tian, G.H. Su, Suizheng Qiu (2025). Integrating Particle Method Simulations and Machine Learning for Predicting Core Melt Flow Pattern. Springer proceedings in physics.DOI
102. Shubiao Dong, Tianrui Li, Chao Tan, Ronghua Chen, Qing Li, Zhigang Hua, Wenxi Tian, Suizheng Qiu (2025). Performance evaluation and adaptive variable-order method of thermal-hydraulic simulations models based on random forests. Annals of Nuclear Energy.DOI
103. Xinkai Wang, Xinkun Xiao, Wen Jiang Ding, Ronghua Chen, Wenxi Tian, Suizheng Qiu, G.H. Su (2025). Numerical Simulation of Flooding Pathways in Nuclear Power Plants by Coupling a Porous Media Model with LSMPS. Springer proceedings in physics.DOI
104. Yue Lin, Dalin Zhang, Yuzhuo Cai, Yapeng Liu, Peng Du, Pengrui Qiao, Wenxi Tian, Suizheng Qiu, Guanghui Su (2025). Numerical study on material behavior and core temperature field evolution under CDAs in LFR. Nuclear Engineering and Technology.DOI
105. Xingguang Zhou, Dalin Zhang, Xinyu Li, Hongxing Yu, Wenxi Tian, Suizheng Qiu, Guanghui Su (2025). Mixed convection in horizontal channel with unstable stratification for low-Prandtl-number fluids. Physics of Fluids.DOI
106. Zhiming Zhu, Kui Zhang, Yangui Yao, Wenxi Tian, Suizheng Qiu (2025). Experimental investigation on natural circulation characteristics of symmetric dual loop under motion conditions. Applied Thermal Engineering.DOI
107. Haocheng Zhang, Panxiao Li, Zhipeng Zhang, Chenglong Wang, Wenxi Tian, Suizheng Qiu (2025). Conceptual design of heat pipe cooled reactor with liquid sodium core for space power systems. Progress in Nuclear Energy.DOI
108. Shaopeng He, Mingjun Wang, Nicola Forgione, Andrea Pucciarelli, Wenxi Tian, Suizheng Qiu, G.H. Su (2025). A multi-task Transformer-Mamba-Seq framework for real-time estimation of spatiotemporal thermal stratification in passive residual heat exchanger. International Communications in Heat and Mass Transfer.DOI
109. Yuzhuo Cai, Dalin Zhang, Yue Lin, Peng Du, Bo Wang, Lina Zhu, Wenxi Tian, Suizheng Qiu, G.H. Su (2025). Thermal-hydraulics analysis of a small lead-cooled fast reactor with reactor vessel cooling system using ACENA. Annals of Nuclear Energy.DOI
110. J.H. Wang, Jinyuan Wang, Panxiao Li, Chenglong Wang, Wenxi Tian, Guanghui Su, Suizheng Qiu (2025). Numerical investigation of high-temperature heat pipe bundle failure scenario for heat pipe cooled reactor. Progress in Nuclear Energy.DOI
111. Xin Yu, Zeqin Zhang, Xiaoyan Wang, Tianyuan Liu, Kailun Guo, Haocheng Zhao, Chunping Tian, Mingjun Wang, Suizheng Qiu, Guanghui Su, Wenxi Tian (2025). Deep learning-based model for predicting physical fields during frozen startup of high-temperature heat pipes. International Journal of Thermal Sciences.DOI
112. Qianxi Xiao, Chao Wang, Ronghua Chen, Guoqing Lu, Dezhi Wan, Liqun Zhang, Changjiang Yang, Wenxi Tian, Suizheng Qiu (2025). VITARS platform: Development and application in nuclear power plant safety analysis. Progress in Nuclear Energy.DOI
113. Haocheng Zhao, Zhao Xin Jin, Chenglong Wang, Jing Zhang, Suizheng Qiu, Wenxi Tian, G.H. Su (2025). Steady-state thermoelectric coupling characteristics analysis of the thermionic space nuclear reactor based on OpenFOAM. Applied Thermal Engineering.DOI
114. Shihao Wu, Xiaocheng Wu, Yapei Zhang, Dong Wang, Pengfei Ma, Wenxi Tian, Suizheng Qiu, G.H. Su (2025). Study on eutectic melting and high-temperature oxidation characteristics of Cr coated Zr alloy cladding under steam atmosphere at 1400–1500 °C. Journal of Alloys and Compounds.DOI
115. Jian Yu, Yapei Zhang, Huicong Song, Haotian Lu, Xinhai Zhao, Peng Chen, G.H. Su, Wenxi Tian, Suizheng Qiu (2025). Visualization experiments of the heat transfer and pressure drop characteristics during the particle bed flooding. International Journal of Thermal Sciences.DOI
116. Fanting Xia, Binzhuo Xia, Kun Zhang, Zhan Liu, Di Liu, Wenxi Tian, Suizheng Qiu (2025). Numerical investigation of critical heat flux in single rod channel under extremely low flow conditions. Progress in Nuclear Energy.DOI
117. Xingguang Zhou, Dalin Zhang, Xinyu Li, Wentao Guo, Hongxing Yu, Wenxi Tian, Suizheng Qiu, Guanghui Su (2025). Mean flow characteristics in horizontal and vertical channels with unstable stratification by buoyancy for liquid lead. European Journal of Mechanics - B/Fluids.DOI
118. Zhiyuan Wu, Yanggen Shi, Kepiao Li, Kui Zhang, Wenxi Tian, Suizheng Qiu (2025). Experimental study on boiling heat transfer characteristics in helical coils with large coiled diameters. Annals of Nuclear Energy.DOI
119. Jinlu Huang, Chenglong Wang, Zeqin Zhang, Tiancai Liu, G.H. Su, Wenxi Tian, Suizheng Qiu (2025). Multi-physics coupling analysis of the heat pipe reactor NUSTER-100 core based on external coupling method. Progress in Nuclear Energy.DOI
120. Yue Lin, Dalin Zhang, Yuzhuo Cai, Yapeng Liu, Peng Du, Zhixin Niu, Bo Wang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2025). Numerical study on influence of LFR water-cooled reactor vessel cooling system under unprotected loss of heat sink Accident. Progress in Nuclear Energy.DOI
121. Pengfei Ma, Shihao Wu, Bo Liu, Haoli Wang, Yaping Zhang, Yicong Lan, Dayan Ma, Junkai Deng, Yapei Zhang, Kui Ge, Wenxi Tian, Suizheng Qiu, G.H. Su (2025). Diffusion and dissolution mechanism of CrSi coated Zr alloy by experiments and first principles. Journal of Nuclear Materials.DOI
122. Yihao Yang, Yiheng Fei, Chenglong Wang, Dalin Zhang, Jing Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2025). Experimental study on the radiative heat transfer characteristics of individual droplets in space liquid droplet radiators. Applied Thermal Engineering.DOI
123. Jian Yu, Yapei Zhang, G.H. Su, Wenxi Tian, Suizheng Qiu (2025). Experimental investigation on nanofluid saturated pool boiling CHF with different chemical additives. Progress in Nuclear Energy.DOI
124. Lingyi Zhang, Wenxi Tian, Zhou Peide, Yang Yong, Yufeng Lv, Suizheng Qiu, G.H. Su (2025). Scaling methodology and transient distortion evaluation for loop-type sodium-cooled fast reactors. Nuclear Engineering and Design.DOI
125. Hongquan Liu, Yingwei Wu, Chuan Jing Lu, Zhendong He, Yanan He, Wenxi Tian, Suizheng Qiu (2025). Development and experimental validation of a two-dimensional CFD model for narrow rectangular channel simulations. International Journal of Thermal Sciences.DOI
126. Wen Hua Ding, Ronghua Chen, Xi Wang, Xinkai Wang, Ming-Jia Li, Wenxi Tian, Suizheng Qiu (2025). An improved particle method for simulating three-dimensional fluid–complex–structure interaction with moving polygon wall boundary and hybrid turbulence models. Physics of Fluids.DOI
127. Shuo Guo, Xingguang Zhou, Dalin Zhang, Changzhi Xiao, Zhixin Niu, Wenxi Tian, Suizheng Qiu, G.H. Su (2025). High-fidelity 3D neutronics and thermal-hydraulics coupling analysis of a liquid metal-cooled fast reactor. Annals of Nuclear Energy.DOI
128. Jianghan Fu, Yiheng Fei, Chenglong Wang, G.H. Su, Wenxi Tian, Suizheng Qiu (2025). Modeling and analysis of heat rejection subsystems for space power systems: steady-state and transient thermal management. Applied Thermal Engineering.DOI
129. Z.X. Zhang, Xue Meng, Yugao Ma, Kailun Guo, Shuhua Ding, Chenglong Wang, Xiaoming Chai, Wenxi Tian, Suizheng Qiu, Guanghui Su (2025). Experimental study of heat transfer characteristics of bent high-temperature heat pipe. International Journal of Thermal Sciences.DOI
130. Jian Hui Zhao, Jing Zhang, Yingwei Wu, Guanghui Su, Wenxi Tian, Suizheng Qiu (2025). Analysis of three-dimensional flow field and reactor vessel impact failure in sodium-cooled fast reactor core disruptive accident. Applied Thermal Engineering.DOI
131. Zeqin Zhang, Chenglong Wang, Jinlu Huang, Kailun Guo, Wenxi Tian, Guanghui Su, Suizheng Qiu (2025). Preliminary design and assessment of the residual heat removal system in a nuclear silent heat pipe-cooled reactor. International Journal of Thermal Sciences.DOI
132. Xuan Yang, Quan Li, Jing Zhang, Yingwei Wu, Yanan He, Chenxi Li, Mingjun Wang, Kailun Guo, Chenglong Wang, G.H. Su, Wenxi Tian, Suizheng Qiu (2025). Thermal-mechanical coupling behavior analysis of solid-state constrained component in advanced nuclear energy system. Energy.DOI
133. Zhifan Zhou, Jing Zhang, Yingwei Wu, Mingjun Wang, Yanan He, Kailun Guo, Chenglong Wang, Guanghui Su, Wenxi Tian, Suizheng Qiu (2025). Study of thermo-mechanical failure mechanisms of fuel assemblies for gas-cooled space nuclear propulsion system. Journal of Thermal Stresses.DOI
134. Xinze Li, Bingqian Zhang, Chengcheng Tong, Ronghua Chen, Dalin Zhang, Wenxi Tian, Suizheng Qiu (2025). Thermal mechanical response analysis of the first wall in laser initial confinement fusion reactors. International Journal of Advanced Nuclear Reactor Design and Technology.DOI
135. Qingshan Chen, Qinrui Zhang, Kailun Guo, Mingjun Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2025). Spray breakup and droplets impacting with model transition. Physics of Fluids.DOI
136. Wenqiang Wu, Tao Huang, Peng Du, Zhenyu Feng, Dalin Zhang, Lei Zhou, Gongle Song, Jian Deng, Zhifang Qiu, Wenxi Tian, Suizheng Qiu, G.H. Su (2025). Development of a two-phase flow solver with two-fluid model based on OpenFOAM: Validation against two-phase boiling flow. Annals of Nuclear Energy.DOI
137. Yujian Huang, Zhengyang Dong, Mingjun Wang, Kui Zhang, Suizheng Qiu, G.H. Su, Wenxi Tian (2025). Numerical simulation on thermal-hydraulic-mechanical coupling of core corium migration during severe accidents. Nuclear Engineering and Design.DOI
138. Xingguang Zhou, Da‐Lin Zhang, Xinyu Li, Hongxing Yu, Wenxi Tian, Suizheng Qiu, Guanghui Su (2025). DNS study of turbulent heat transfer with different Prandtl numbers under constant wall-temperature difference condition. Progress in Nuclear Energy.DOI
139. Lining Liu, Jiarui Zhang, Chenglong Wang, Wenxi Tian, Suizheng Qiu, Yugao Ma, Xiaoming Chai (2025). Experimental study of impurity elements influence on heat transfer performance of high temperature sodium heat pipe. Applied Thermal Engineering.DOI
140. Junfeng Liu, Chenglong Wang, Suizheng Qiu, Shifa Wu, Boyuan Wang (2025). An operation optimization of cooling system for reactor shutdown in pebble bed gas-cooled reactor. Journal of Nuclear Science and Technology.DOI
141. Wenxi Tian, Linlin Fei, Chenglong Wang, Kailun Guo, Wenxi Tian, Suizheng Qiu, G.H. Su, Dominique Derome, Jan Carmeliet (2025). Lattice Boltzmann modeling of evaporation of porous media considering conjugate heat transfer. Physics of Fluids.DOI
142. Zeqin Zhang, Zhipeng Zhang, Chenglong Wang, Kailun Guo, Wenxi Tian, Guanghui Su, Suizheng Qiu (2025). Heat pipe-cooled reactors: A comprehensive review of evolution, challenges, research status, and outlook. Renewable and Sustainable Energy Reviews.DOI
143. Yutong Chen, Dalin Zhang, Yue Lin, Di Wang, Zhenyu Feng, Wenxi Tian, Suizheng Qiu, G.H. Su (2025). Research status in safety analysis of steam generator tube rupture accident in lead-based fast reactors – A review. Nuclear Engineering and Design.DOI
144. Xinyang Zhu, Jinshun Wang, Chenfeng Bao, Ronghua Chen, Wenxi Tian, Suizheng Qiu (2025). Development and validation of a subchannel analysis code for PWRs based on the two-phase and three-field model. Progress in Nuclear Energy.DOI
145. Z Li, Lanfei Yuan, Chenglong Wang, Suizheng Qiu, Ying Hui Li (2025). Development and Performance Analysis of an Electromagnetic Pump for a Thermal Hydraulic Experimental Loop of a Lead-Cooled Fast Reactor. Energies.DOI
146. Defang Mu, Mingjun Wang, Kailun Guo, Hang Zang, Wenxi Tian, G.H. Su, Suizheng Qiu (2025). Particle trajectory and deposition in contraction–expansion flow fields using coupled large eddy simulation and discrete phase model. Physics of Fluids.DOI
147. Songsheng Tang, Kailun Guo, Wenxiang Gao, Mingjun Wang, Chenglong Wang, Yugao Ma, G.H. Su, Suizheng Qiu, Wenxi Tian (2025). Wetting and evaporation of alkali metal sodium droplets on 304 stainless steel. Applied Thermal Engineering.DOI
148. Shihao Wu, Yapei Zhang, Jian Yu, Jingyuan Bai, Wenxi Tian, Suizheng Qiu, G.H. Su (2025). Experimental research on heat transfer characteristics of a two-layer corium pool based on a three-dimensional ellipsoidal lower plenum. Frontiers in Nuclear Engineering.DOI
149. Jinshun Wang, Ronghua Chen, Sicong Xiao, Xinyang Zhu, Minyang Gui, Wenxi Tian, Suizheng Qiu (2025). Parallelization and application of SACOS-LMR for whole-core pin-by-pin thermal-hydraulic analysis in LMFRs. Annals of Nuclear Energy.DOI
150. Jinshun Wang, Ronghua Chen, Liang Yu, Minyang Gui, Xinyang Zhu, Wenxi Tian, Suizheng Qiu (2025). Development and application of sub-channel thermal-hydraulic analysis code for liquid metal cooled reactors. Nuclear Engineering and Technology.DOI
151. Zhenyu Feng, Dalin Zhang, Wenqiang Wu, Haodong Guo, Xilin Zhang, Xiaoyu Wang, Jian Deng, Wenxi Tian, Suizheng Qiu, Guanghui Su (2025). Numerical study on the thermal stratification characteristics of the primary system for Lead-based cooled Fast Reactor. Nuclear Engineering and Technology.DOI
152. Wenqiang Wu, Tao Huang, Peng Du, Dalin Zhang, Lei Zhou, Bo Wang, Jian Deng, Zhifang Qiu, Wenxi Tian, Suizheng Qiu, G.H. Su (2025). Development of a two-phase flow solver with drift-flux model based on OpenFOAM: Validation against single/two-phase and boiling flow. Annals of Nuclear Energy.DOI
153. 陈诺，赖志贤，王世奇，王明军，田文喜，秋穗正，苏光辉（2024）. 基于欧拉-欧拉两相流模型的核事故放射性物质扩散特性数值模拟. 《火箭军工程大学学报》.
154. 陈荣华，田文喜，郭凯伦，张魁，秋穗正，苏光辉（2024）. 核反应堆两相流和严重事故关键现象粒子法模拟研究. 《中国科学:技术科学》.
155. 周之帆，章静，巫英伟，贺亚男，郭凯伦，王明军，苏光辉，秋穗正，田文喜（2024）. 核热推进反应堆燃料元件热工应力安全分析. 《火箭推进》.
156. 李昕泽，张冰倩，陈荣华，张魁，张大林，田文喜，秋穗正，苏光辉（2024）. 激光惯性约束聚变堆包层能量沉积特性. 《强激光与粒子束》.
157. 刘俊峰，王成龙，秋穗正，李文姝，苏光辉，田文喜，马晓珑（2024）. 高温气冷堆热态功能试验中一回路加热动态特性研究. 《核科学与工程》.
158. 陈青山，王明军，田文喜，秋穗正，苏光辉（2024）. 四进口切向离心喷嘴的设计方法和模拟验证研究. 《核科学与工程》.
159. 巫英伟，贺亚男，章静，田文喜，苏光辉，秋穗正（2024）. 核反应堆系统多维度多物理场耦合有限元分析研究. 《原子能科学技术》.
160. 肖常志，杨红义，张大林，沈格宇，秋穗正，路远，张魁，黄源彬（2024）. 快堆钠-水蒸汽发生器热工水力稳态综合性能研究. 《原子能科学技术》.
161. 赵昊城，张泽秦，王成龙，秋穗正，田文喜，苏光辉（2024）. 基于有限体积法碱金属高温热管冷态启动流动换热数值研究. 《原子能科学技术》.
162. 王心安，张大林，王婷，秋穗正，苏光辉（2024）. 一种适用于钠冷快堆绕丝棒束组件热工水力特性分析的多孔介质模型. 《核动力工程》.
163. 王金顺，陈荣华，朱昕阳，田家豪，田文喜，秋穗正，苏光辉（2024）. 液态金属冷却快堆子通道分析软件SACOS-LMR研发与工程应用. 《原子能科学技术》.
164. 姜殿强，张大林，陈凯龙，田文喜，秋穗正，苏光辉（2024）. 熔盐沿螺旋十字型单棒层流混合对流传热数值研究. 《核动力工程》.
165. 岳智瑛，贺亚男，刘洪权，巫英伟，章静，苏光辉，田文喜，秋穗正（2024）. 板状燃料富集度对燃料性能的影响研究. 《核技术》.
166. 陈楠，向烽瑞，贺亚男，巫英伟，章静，苏光辉，田文喜，秋穗正（2024）. 压水堆棒状燃料氧化与吸氢模型开发及验证. 《核技术》.
167. 杨轩，李权，李晨曦，章静，巫英伟，贺亚男，郭凯伦，苏光辉，田文喜，秋穗正（2024）. 热管堆固态堆芯燃料辐照-热-力耦合性能分析. 《核技术》.
168. 向烽瑞，贺亚男，巫英伟，秋穗正，苏光辉（2024）. 弥散型板状燃料元件跨尺度耦合特性计算与分析. 《核动力工程》.
169. 张睿潇，贺亚男，巫英伟，田文喜，秋穗正，苏光辉（2024）. 多层各向异性包壳力学模型开发与应用. 《核动力工程》.
170. 王锦源，李潘潇，王成龙，张泽秦，田文喜，秋穗正，苏光辉（2024）. 热管失效对高温热管管束及基体影响实验研究. 《核动力工程》.
171. 张凌义，张智鹏，王成龙，郭凯伦，田文喜，苏光辉，秋穗正（2024）. 高温钠热管启动传热振荡及热疲劳安全分析. 《原子能科学技术》.
172. 刘雅鹏，张大林，陈宇彤，周磊，田文喜，秋穗正，苏光辉（2024）. 基于ACENA程序的凤凰堆自然循环试验数值模拟. 《核动力工程》.
173. 张吉，王莹杰，王明军，田文喜，秋穗正，苏光辉（2024）. 基于CFD方法的铅铋堆组件操作头射流搅混特性研究. 《核动力工程》.
174. 刘雅鹏，张大林，陈宇彤，林悦，张熙司，田文喜，秋穗正，苏光辉（2024）. 熔融不锈钢与液态钠相互作用的瞬态换热特性研究. 《原子能科学技术》.
175. 朱昕阳，陈荣华，王金顺，田家豪，秋穗正，苏光辉，田文喜（2024）. 基于有限元方法的液态金属子通道程序开发与验证. 《原子能科学技术》.
176. 陈宇彤，张大林，林悦，张熙司，田文喜，秋穗正，苏光辉（2024）. 池式铅冷快堆SGTR事故多组分多相流动过程数值模拟研究. 《原子能科学技术》.
177. 田文喜，王成龙，郭凯伦，秋穗正，苏光辉（2024）. 热管冷却反应堆系统研究进展和挑战. 《原子能科学技术》.
178. 陈诺，马俊，张吉，王明军，田文喜，苏光辉，秋穗正（2024）. 不溶性腐蚀产物在棒束通道内沉积的数值模拟. 《核科学与工程》.
179. 杨宇鹏，王成龙，张大林，苏光辉，秋穗正，田文喜（2024）. 基于多孔介质方法的铅铋螺旋管式直流蒸汽发生器设计优化研究. 《核科学与工程》.
180. Xindi Lv, Dalin Zhang, Xinyu Li, Xingguang Zhou, Dianqiang Jiang, Guanghui Su, Wenxi Tian, Suizheng Qiu (2024). Study on the safety characteristics of fluoride-salt-cooled high-temperature advanced reactor. Annals of Nuclear Energy.DOI
181. Shuo Liu, Jin Zhao, Chenglong Wang, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su, Jun Yang (2024). Development of modular dynamic code for steam power conversion system in sodium-cooled fast reactor. Progress in Nuclear Energy.DOI
182. Wenshu Li, Junfeng Liu, Chenglong Wang, Bo Wang, Suizheng Qiu, G.H. Su, Wenxi Tian (2024). Three-dimensional thermal–mechanical analysis of helical coil once-through steam generator. Applied Thermal Engineering.DOI
183. Zeqin Zhang, Haocheng Zhao, Chenglong Wang, Kailun Guo, G.H. Su, Wenxi Tian, Suizheng Qiu (2024). Study on the start-up characteristics of a 100kWe-level nuclear silent heat pipe cooled reactor based on cascaded control. Energy.DOI
184. Xiao Pang, Dingsheng Lu, Chenglong Wang, Suizheng Qiu, Wenxi Tian, G.H. Su (2024). Numerical investigation of impurity deposition and filtration characteristics for lead-bismuth eutectic cooled system. Annals of Nuclear Energy.DOI
185. Songjiao Yu, Kui Zhang, Yiming Yang, Yumin Liu, Wenxi Tian, Suizheng Qiu, Jianjun Xu, Lei Ding (2024). A preliminary study on the blistering behavior of dispersion plate-type fuel assembly. Annals of Nuclear Energy.DOI
186. Shaopeng He, Yongkang Ye, Mingjun Wang, Jing Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2024). A machine learning and CFD based approach for fouling rapid prediction in shell-and-tube heat exchanger. Nuclear Engineering and Design.DOI
187. Binzhuo Xia, Kui Zhang, Ronghua Chen, Wenxi Tian, Suizheng Qiu (2024). Review of CHF experiment and prediction methods under motion condition. Nuclear Engineering and Design.DOI
188. Fengtao Zhang, Xin Rong Duan, Jing Zhang, Quan-yao Ren, Yingwei Wu, Quan Li, Suizheng Qiu (2024). Filtration performance and hydraulic characteristic analysis on the bottom nozzle in a fuel assembly of a nuclear energy system. Physics of Fluids.DOI
189. Pengfei Ma, Xiaocheng Wu, Yapei Zhang, Dong Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2024). Study of atomic sputtering and transport dynamics by Monte Carlo simulation. Nuclear Engineering and Technology.DOI
190. Haocheng Zhao, Chenglong Wang, Suizheng Qiu, Wenxi Tian, Guanghui Su (2024). Thermo-electric characteristics analysis of thermionic energy conversion in space nuclear reactors. Applied Thermal Engineering.DOI
191. Kepiao Li, Kui Zhang, Tianyi Qi, Ronghua Chen, Wenxi Tian, Suizheng Qiu (2024). Boiling critical characteristics in narrow rectangular channel under local heat flux concentration conditions. Annals of Nuclear Energy.DOI
192. Yue Lin, Dalin Zhang, Yutong Chen, Xisi Zhang, Jian Deng, Wenxi Tian, Suizheng Qiu, G.H. Su (2024). Preliminary development and validation of ACENA code for melting and freezing behavior simulation. Annals of Nuclear Energy.DOI
193. Yue Lin, Dalin Zhang, Yutong Chen, Xisi Zhang, Jian Deng, Peng Du, Wenxi Tian, Suizheng Qiu, Guanghui Su (2024). Numerical study on the impact characteristics of molten lead-bismuth droplets into water. Nuclear Engineering and Design.DOI
194. Changzhong Li, Chenglong Wang, Yanyu Sun, Ronghua Chen, Wenxi Tian, G.H. Su, Suizheng Qiu (2024). Experimental investigation on flow and heat transfer characteristics of helium in rectangular narrow slit channel. International Journal of Thermal Sciences.DOI
195. Kepiao Li, Zhiyuan Wu, Kui Zhang, Wenxi Tian, Suizheng Qiu (2024). Experimental and theoretical research on upper plenum entrainment with air-water and steam-water. Progress in Nuclear Energy.DOI
196. Lei Zhou, Dalin Zhang, Yapeng Liu, Liang Yu, Bo Wang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2024). Direct numerical simulation of sodium in vertical channel flow: From forced convection to natural convection at friction Reynolds number 180. Physics of Fluids.DOI
197. Wenxi Tian, Jiarui Zhang, Chenglong Wang, Kailun Guo, Wenxi Tian, Suizheng Qiu, Guanghui Su (2024). Design, fabrication, and comparative analysis of prototype high-temperature heat pipes charged with sodium for heat pipe cooled reactor NUSTER-100. Applied Thermal Engineering.DOI
198. Binzhuo Xia, Fanting Xia, Kui Zhang, Ronghua Chen, Wenxi Tian, Suizheng Qiu (2024). Experimental study of boiling critical heat flux with low mass flux under motion condition in a wetted perimeter equivalent rod. Applied Thermal Engineering.DOI
199. Yiwen Chen, Dalin Zhang, Dianqiang Jiang, Wei Li, Qi Lu, Wenxi Tian, Suizheng Qiu, G.H. Su (2024). Thermal-mechanical influence aspects and evaluation of helical cruciform single rod in fluoride-salt-cooled high-temperature advanced reactor. International Journal of Thermal Sciences.DOI
200. Yujian Huang, Mingjun Wang, Suizheng Qiu, Kui Zhang, Wenxi Tian, Zhen Zhang (2024). Numerical study on the thermal hydraulic characteristics of ERVC system. Annals of Nuclear Energy.DOI
201. Haocheng Zhao, Zeqin Zhang, Chenglong Wang, Suizheng Qiu, Wenxi Tian, Guanghui Su (2024). Operation characteristics analysis of high temperature alkali metal heat pipe based on OpenFOAM. Applied Thermal Engineering.DOI
202. Zichao Han, Jing Zhang, Mingjun Wang, Wenxi Tian, Guanghui Su, Suizheng Qiu (2024). Steady-state thermal–hydraulic analysis of an NTP reactor core based on the porous medium approach. Annals of Nuclear Energy.DOI
203. Zhiyuan Wu, Kepiao Li, Kui Zhang, Ronghua Chen, Wenxi Tian, Suizheng Qiu (2024). Experimental study on the plate-type fuel melting behavior based on alternative materials. Annals of Nuclear Energy.DOI
204. Xinyu Li, Dalin Zhang, Dianqiang Jiang, Xingguang Zhou, Xindi Lv, Wenxi Tian, Suizheng Qiu, G.H. Su (2024). Review, numerical validation, and experiment verification for Definite solution Analogy Theory (DSAT) in thermal-hydraulic scaling. Applied Thermal Engineering.DOI
205. Zhiming Zhu, Kui Zhang, Kepiao Li, Hao Fu, Wenxi Tian, Suizheng Qiu (2024). Experimental Study of Single and Two-Phase Flow and Heat Transfer Characteristics in Helical Tube under Motion Condition. Heat Transfer Engineering.DOI
206. Yan Zhang, Yan Zhang, Bo Wang, Dalin Zhang, Chenglong Wang, Yang Yang, Zhengrong Guo, Wenxi Tian, Guanghui Su, Suizheng Qiu (2024). Coupled analysis of oxidation corrosion and heat transfer in lead-cooled fast reactors. Annals of Nuclear Energy.DOI
207. Kepiao Li, Zhiyuan Wu, Kui Zhang, Wenxi Tian, Xinran Ma, Suizheng Qiu (2024). Experimental study on effect of pressure on ADS-4 liquid entrainment characteristics in T-junction. Progress in Nuclear Energy.DOI
208. Qifan Yu, Hongjian Guo, Suizheng Qiu, Chenglong Wang, Dalin Zhang, Wenxi Tian, Guanghui Su (2024). Separate effect experimental test and theoretical investigate of pressure wave propagation and pressure rising process upon SGTR accident in advanced LFRs. Nuclear Engineering and Design.DOI
209. Kai Liu, Jinxiang Sun, Mingjun Wang, Jing Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2024). Experimental study on flow and heat transfer of High-Pressure helium flow in compact helical tube heat exchanger in HTGR. Applied Thermal Engineering.DOI
210. Yupeng Yang, Dingsheng Lu, Chenglong Wang, Dalin Zhang, Suizheng Qiu, G.H. Su, Wenxi Tian (2024). Numerical study on heat transfer characteristics of LBE cross flow tube bundle under rolling conditions. Annals of Nuclear Energy.DOI
211. Shuowang Fan, Yutong Chen, Dalin Zhang, Jian Deng, Xisi Zhang, Xiaoli Wu, Wenxi Tian, Suizheng Qiu, Guanghui Su (2024). Experimental study on fragmentation characteristics of molten stainless steel discharged into liquid Lead-Bismuth Eutectic pool. Annals of Nuclear Energy.DOI
212. H. B. Li, Dalin Zhang, Lei Zhou, Jian Deng, Wenxi Tian, G.H. Su, Suizheng Qiu (2024). Numerical study on benchmark analysis of NACIE-UP facility with uniform and non-uniform power distribution. Annals of Nuclear Energy.DOI
213. Kailun Guo, Qishi Sun, Hao Xuan Sun, Chenlong Wang, Kang Chen, Wenxi Tian, Guanghui Su, Suizheng Qiu (2024). Numerical Investigation of High-Temperature Heat Pipes With Different Wick Structures Under Non-Uniform Heating Boundary Conditions.DOI
214. Zhengyang Dong, Kai Liu, Mingjun Wang, Junmei Wu, Wenxi Tian, Suizheng Qiu, Guanghui Su (2024). Development of Two-Dimensional Heat Conduction Model in Subchannel Code Based on OpenFOAM.DOI
215. Zhenyu Feng, Dalin Zhang, Haoyu Jiao, Yutong Chen, Yue Lin, Wenxi Tian, Suizheng Qiu, G.H. Su (2024). Study on Bubble Migration Characteristics in a Lead-Cooled Fast Reactor After Steam Generator Tube Rupture Accident.DOI
216. Chen Qingshan, Mingjun Wang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2024). Multi-Objective Optimization Study of Nozzle Outlet Size Based on Atomization Performance.DOI
217. Yutong Chen, Dalin Zhang, Zhenyu Feng, Yue Lin, Wenxi Tian, Suizheng Qiu, G.H. Su (2024). Numerical Investigation of Postulated Steam Generator Tube Rupture Accident in a Lead-Cooled Fast Reactor.DOI
218. Jian Hui Zhao, Jing Zhang, Yingwei Wu, Guanghui Su, Wenxi Tian, Suizheng Qiu (2024). Numerical Analysis of Three-Dimensional Flow Field Impact Under Strong Transient Conditions in Advanced Reactors.DOI
219. Dingsheng Lu, Yupeng Yang, Xiao Pang, Chenglong Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2024). Numerical Simulation of Agglomeration Characteristics of Liquid Lead-Bismuth Eutectic (LBE) Impurity Particles.DOI
220. Zhipeng Zhang, Chenglong Wang, Kailun Guo, Wenxi Tian, Guanghui Su, Suizheng Qiu (2024). Study of Gravity Effect on the Operating Characteristics of High-Temperature Bent Heat Pipes.DOI
221. Guorui Yang, Jing Zhang, Yingwei Wu, Yanan He, Suizheng Qiu, Guanghui Su, Wenxi Tian (2024). Experimental Study of Bubble Migration Characteristics in MCCI Molten Pool.DOI
222. Ji Zhang, Mingjun Wang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2024). Study of Jet Characteristics and Structural Fatigue in the Upper Chamber of a Lead-Bismuth Eutectic Cooled Reactor Based on Fluid-Structure Coupling Methods.DOI
223. Wenqiang Wu, Dalin Zhang, Tao Huang, Lei Zhou, Peng Du, Wenxi Tian, Suizheng Qiu, Guanghui Su (2024). Development and Validation of a Two-Phase Flow Solver With Drift-Flux Model Based on OpenFOAM.DOI
224. Defang Mu, Jie Rong, Mingjun Wang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2024). Investigating the Motion Characteristics of Complex-Shaped Foreign Objects on the Secondary Side of a Steam Generator Based on CFD-DEM Method.DOI
225. Yapeng Liu, Bo Wang, Dalin Zhang, Zhenyu Feng, Xinyu Li, Wenxi Tian, Suizheng Qiu, G.H. Su (2024). Study on Radial Thermal-Hydraulic Characteristics of Once-Through Steam Generator of Sodium-Cooled Fast Reactor.DOI
226. Xinze Li, Ronghua Chen, Bingqian Zhang, Kui Zhang, Dalin Zhang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2024). Preliminary Study on Laser Inertial Confinement Fusion Reactor Energy Transfer.DOI
227. Binzhuo Xia, Fanting Xia, Yiming Yang, Kui Zhang, Ronghua Chen, Wenxi Tian, Suizheng Qiu (2024). PERFORM: High Temperature and Pressure CHF Experiment Bench Under Six Degrees of Freedom Motion Condition.DOI
228. Yixin Zhang, Chenglong Wang, Jiaxin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2024). Research on Multi-Scale Coupling Program Based on Lead Bismuth Fast Reactor.DOI
229. Shuo Liu, Chenglong Wang, Suizheng Qiu, Wenxi Tian, Guanghui Su (2024). Temperature Field Rapid Estimation of Space Nuclear Thermionic Reactor Based on Reduced-Order Model.DOI
230. Menghao Luo, Zhiwei Lü, Yanan He, Yingwei Wu, Wenxi Tian, Guanghui Su, Suizheng Qiu (2024). Study on Heat Transfer Characteristics of 2×2 Helical Cruciform Fuel Assembly Under Non-Uniform Heat Source.DOI
231. Shuowang Fan, Yutong Chen, Dalin Zhang, Xiaoli Wu, Wenxi Tian, Suizheng Qiu, Guanghui Su (2024). Numerical Study on Molten Stainless Steel and Lead Bismuth Eutectic Interaction for Lead-Cooled Fast Reactors Using the ACENA Code With Experimental Validation.DOI
232. Jiarui Zhang, Chenglong Wang, Zhixing Tian, Kailun Guo, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2024). Design, Development and Testing of Large Diameter High Temperature Alkaline Metal Heat Pipe.DOI
233. Songsheng Tang, Kailun Guo, Shiyu Tian, Yugao Ma, Jinkun Zhao, G.H. Su, Suizheng Qiu, Wenxi Tian (2024). Evaporation of Alkali Metal Sodium Droplet in the Circular Tube.DOI
234. Yin Zhang, Kailun Guo, Chenglong Wang, Jing Lin Zhang, Yulu Wang, Tianwen Xi, G.H. Su, Suizheng Qiu (2024). Artificial neural network for geometric design and optimization of three-stage segmented thermoelectric generators. Applied Thermal Engineering.DOI
235. Songsheng Tang, Kailun Guo, Ruibo Zhang, Mingjun Wang, Chenglong Wang, Xiaoqiang He, G.H. Su, Suizheng Qiu, Wenxi Tian (2024). Investigations of sodium droplet spreading and evaporation on surfaces with different wettability based on lattice Boltzmann simulations. Annals of Nuclear Energy.DOI
236. Hongjian Guo, Wei Li, Jing Zhang, Yingwei Wu, Pingting Jiang, Mingjun Wang, Suizheng Qiu, G.H. Su, Wenxi Tian (2024). Numerical investigation on the effect of different factors on the flow-induced vibration of wire-wrapped fuel rod under axial flow. Annals of Nuclear Energy.DOI
237. Shihao Wu, Dong Wang, Yapei Zhang, Xiaocheng Wu, Wenxi Tian, Suizheng Qiu, G.H. Su (2024). Performance evaluation of accident tolerant Cr-coated Zr alloy cladding under accident conditions based on a refined degradation model. Progress in Nuclear Energy.DOI
238. Pengfei Ma, Dong Wang, Xiaocheng Wu, Yapei Zhang, Wenxi Tian, G.H. Su, Suizheng Qiu (2024). Understanding ion transport mechanisms of chromium-coated zirconium alloy cladding in steam oxidation. Surface and Coatings Technology.DOI
239. Yiheng Fei, Jianghan Fu, Chenglong Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2024). Numerical study of anisotropic scattering and solar radiation impact on liquid droplet radiator performance. Applied Thermal Engineering.DOI
240. Zhenyu Feng, Dalin Zhang, Yi‐Wen Chen, Yangchun Pu, Shichang Yun, Sisi Wang, Caihong Xu, Dongyu He, Ting Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2024). Integral validation for two-fluid thermal hydraulic system analysis code LOCUST 1.2 based on LOFT L9-3 experiment. Annals of Nuclear Energy.DOI
241. Qingshan Chen, Qinrui Zhang, Qianglong Wang, Kailun Guo, Mingjun Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2024). Numerical study and experimental validation: A portioned calculation method for a large atomization field. Physics of Fluids.DOI
242. Kailun Guo, Yu-Bao Zhong, Sijun Li, Ronghua Chen, Mingjun Wang, Yulu Wang, Suizheng Qiu, Wenxi Tian (2024). Numerical investigations of the Kelvin-Helmholtz instability based on a multi-resolution Moving particle Semi-implicit method. Nuclear Engineering and Design.DOI
243. Jiaxin Zhang, Chenglong Wang, Wenxi Tian, G.H. Su, Suizheng Qiu, Xian Lin, Kun Cheng, Xiao Chu, Shiying Wei, Guo Chen (2024). Safety analysis code development and validation for lead-cooled fast reactor with helical coiled once-through steam generator. Annals of Nuclear Energy.DOI
244. Wen Hua Ding, Fangfang Fang, Ronghua Chen, Kun Han, Liangpeng Wu, Wenxi Tian, Suizheng Qiu, G.H. Su (2024). Experimental and numerical research on the debris bed formation in severe accidents of nuclear reactors. International Journal of Thermal Sciences.DOI
245. Junfeng Liu, Chenglong Wang, Suizheng Qiu, Lining Dong (2024). Variable universe fuzzy control of once-through steam generator feedwater. Annals of Nuclear Energy.DOI
246. Zhenglong Liu, Mingjun Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2024). Flow mixing and heat transfer deterioration investigation of supercritical carbon dioxide in wire-wrapped bundles. Applied Thermal Engineering.DOI
247. Yiwen Chen, Dalin Zhang, Dianqiang Jiang, Jian Deng, Xisi Zhang, Xin’an Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2024). Thermal-hydraulic characteristics of helical cruciform single rod based on CFD investigation. Annals of Nuclear Energy.DOI
248. Z.X. Zhang, Panxiao Li, Chenglong Wang, Kailun Guo, Wenxi Tian, Suizheng Qiu, G.H. Su (2024). Conceptual design of a mobile nuclear-electric hybrid energy storage system based on the heat pipe-cooled reactor. Nuclear Engineering and Design.DOI
249. Yanggen Shi, Kepiao Li, Kui Zhang, Wenxi Tian, Suizheng Qiu (2024). Experimental study and theoretical development of liquid entrainment in T-junction with double inlets and single inlet of gas phase. Progress in Nuclear Energy.DOI
250. Xiaocheng Wu, Dong Wang, Yapei Zhang, X.J. Li, Shihao Wu, G.H. Su, Suizheng Qiu, Wenxi Tian, Ruhao Zhong, Yehong Liao, Zhenxun Peng (2024). Isothermal experiments on eutectic and oxidation reactions of Cr-coated Zr alloy cladding in steam at 1350 ℃: Behavior, mechanism and kinetics. Journal of Alloys and Compounds.DOI
251. Jie Cai, Kun Zhang, Xinran Ma, Tianyu Chen, Wenxi Tian, Suizheng Qiu (2024). Numerical study on the condensation characteristics of vapor with non-condensable gas on inclined walls inside containment. Annals of Nuclear Energy.DOI
252. Ruiyu Sun, Minyang Gui, Jinshun Wang, Ronghua Chen, Kui Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2024). SACOS-PLATE: A new thermal-hydraulic subchannel analysis code for plate type fuel assemblies. Annals of Nuclear Energy.DOI
253. Dong Wang, Ruhao Zhong, Xiaocheng Wu, Yapei Zhang, X.J. Li, Jian Yu, Yicong Lan, G.H. Su, Suizheng Qiu, Wenxi Tian, Yehong Liao, Zhenxun Peng, Chao Guo, Zhongxiao Song, Jun Sun (2024). Study on eutectic-oxidation coupling reaction of Cr-Zr system in high temperature steam environment. Journal of Nuclear Materials.DOI
254. Xinhai Zhao, Yicong Lan, Peng Chen, Yapei Zhang, Haoli Wang, Chao Guo, Simin Luo, Wenxi Tian, G.H. Su, Suizheng Qiu (2024). Experiment study on the flow mechanism of the molten pool relocation using simulant materials at room temperature. Progress in Nuclear Energy.DOI
255. Chenglong Wang, Chenglong Wang, Chen Wang, Chen Wang, Wenxi Tian, G.H. Su, Suizheng Qiu (2024). Effect analysis of oxide layer on thermal hydraulic characteristics of LBE cooled reactor. Annals of Nuclear Energy.DOI
256. Y.P Zhang, Chenglong Wang, Wenxi Tian, Suizheng Qiu, G.H. Su, Lin Chao (2024). Thermal and hydraulic characteristics analysis of horizontal lead-bismuth reactor assembly based on sub-channel analysis code. Progress in Nuclear Energy.DOI
257. Haoli Wang, Simin Luo, Xinhai Zhao, Yapei Zhang, Yicong Lan, Xiaocheng Wu, Dong Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2024). High-temperature steam oxidation experiment of molten zirconium alloy. Corrosion Science.DOI
258. Yongjun Jiao, Yihu Wang, Wei Li, Meiyin Zheng, Jing Zhang, Yingwei Wu, G.H. Su, Suizheng Qiu (2024). Numerical simulation investigations on the flow induced vibration of a nuclear fuel rod with relaxed clamping structures. Annals of Nuclear Energy.DOI
259. Yue Li, Linrong Ye, Mingjun Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2024). Numerical investigations on the droplet moving in steam with non-condensable gas by lattice Boltzmann method. International Journal of Thermal Sciences.DOI
260. Dianqiang Jiang, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2024). Experimental study on flow and heat transfer of medium-Prandtl-number fluid along a hexagonal helical cruciform seven-rods. International Journal of Heat and Mass Transfer.DOI
261. Yichao Ma, Dexiang Kong, Jing Zhang, Mingjun Wang, Wenxi Tian, Yingwei Wu, G.H. Su, Suizheng Qiu (2024). Study on flow regime prediction model for water-cooled reactor core based on machine learning algorithms. Annals of Nuclear Energy.DOI
262. Zhipeng Liu, Wenxi Tian, Chenglong Wang, Dalin Zhang, Kui Zhang, Suizheng Qiu, G.H. Su (2024). Experimental study of the influence of buoyancy on turbulent mixed convection in lead–bismuth eutectic flow under inclination conditions. Applied Thermal Engineering.DOI
263. Xingguang Zhou, Dalin Zhang, Lei Zhou, Wenqiang Wu, Xisi Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2024). Development and validation of a neutron transport solver with SP 3 method based on OpenFOAM. Progress in Nuclear Energy.DOI
264. Chenglong Wang, Chenglong Wang, Chen Wang, Chen Wang, Wenxi Tian, Guanghui Su, Suizheng Qiu (2024). Code development and preliminary validation for lead-cooled fast reactor thermal-hydraulic transient behavior. Nuclear Engineering and Technology.DOI
265. Xingguang Zhou, Dalin Zhang, Xinyu Li, Jian Deng, Wenxi Tian, Suizheng Qiu, G.H. Su, Xiaoqiang He, Hongxing Yu (2024). Development of a neutron space–time kinetics solver with improved quasi-static method based on OpenFOAM. Nuclear Engineering and Design.DOI
266. Shiqi Wang, Shiqi Wang, Shaopeng He, Mingjun Wang, Wenxi Tian, G.H. Su, Suizheng Qiu (2024). Two parallel methods for the three-dimensional CFD coupling simulation of shell and tube heat exchangers. Annals of Nuclear Energy.DOI
267. Jianghan Fu, Jin Hao Zhao, Zhiwen Dai, G.H. Su, Chenglong Wang, Wenxi Tian, Suizheng Qiu (2024). Model predictive control for automatic operation of space nuclear reactors: Design, simulation, and performance evaluation. Annals of Nuclear Energy.DOI
268. Shuo Guo, Dalin Zhang, Xinyu Li, Xuanang He, Hongda Wang, Jian Deng, Xisi Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2024). Exergy analysis of biomass and nuclear hydrogen production system. International Journal of Hydrogen Energy.DOI
269. Wen Hua Ding, Kui Zhang, Ronghua Chen, Wenxi Tian, Suizheng Qiu (2024). Development of thermo-physical property database and code of fusion materials for CFETR blankets. Progress in Nuclear Energy.DOI
270. H. B. Li, Dalin Zhang, Hao Qin, Xinyu Li, Jian Deng, Wenxi Tian, G.H. Su, Suizheng Qiu (2024). Study on tritium transport characteristics in fluoride-salt-cooled high-temperature advanced reactor. International Journal of Hydrogen Energy.DOI
271. Yuan Lanfei, Ziang Li, Wang Chenglong, Qiu Suizheng (2024). Experimental and model development of lead-bismuth eutectic solidification phenomenon flowing inside the tube. Progress in Nuclear Energy.DOI
272. Chen Shikang, Chen Ronghua, Qiu Suizheng (2024). Reliability Quantification of Passive Containment Cooling System Through Response Surface Methodology.DOI
273. 林悦，张大林，陈宇彤，张熙司，田文喜，秋穗正，苏光辉（2023）. 熔融铅铋与水相互作用热工水力特性研究. 《原子能科学技术》.
274. 王栋，钟汝浩，张亚培，郭超，徐浩德，余剑，蓝毅聪，苏光辉，秋穗正，田文喜（2023）. 磁控溅射铬涂层锆合金包壳高温水蒸气氧化行为. 《表面技术》.
275. 叶天舟，姚欢，巫英伟，章静，王明军，陈平，田文喜，秋穗正，苏光辉（2023）. FeCrAl合金拉伸力学性能分子动力学研究. 《稀有金属材料与工程》.
276. 董正阳，刘凯，王明军，田文喜，秋穗正，苏光辉（2023）. CorTAF2.0核热耦合及杂质沉积模块开发及初步应用. 《原子能科学技术》.
277. 刘奚彤，刘凯，王明军，王啸宇，田文喜，秋穗正，苏光辉（2023）. 弯曲变形工况下板状燃料堆芯三维热工水力特性分析. 《原子能科学技术》.
278. 赵亚峰，刘志鹏，王成龙，于启帆，苏光辉，秋穗正，田文喜（2023）. 起伏对强迫循环下铅铋合金阻力及换热特性影响实验研究. 《原子能科学技术》.
279. 张凌义，李潘潇，张胤，王成龙，田文喜，苏光辉，秋穗正（2023）. 双模式热管堆非核原理样机热力特性数值分析. 《原子能科学技术》.
280. 刘杰，张大林，周星光，林超，田文喜，苏光辉，秋穗正（2023）. 六边形组件棒束通道内液态铅铋流动传热特性实验研究. 《原子能科学技术》.
281. 袁蓝飞，王成龙，刘志鹏，苏光辉，秋穗正，田文喜（2023）. 横摇运动下铅铋回路热工水力特性数值研究. 《原子能科学技术》.
282. 王栋，葛魁，张亚培，胡亮，苏光辉，秋穗正，田文喜（2023）. 钠冷快堆熔融物碎片流重定位行为数值模拟研究. 《原子能科学技术》.
283. 向烽瑞，贺亚男，邓超群，牛钰航，高士鑫，巫英伟，陈平，田文喜，秋穗正，苏光辉（2023）. Cr涂层对板状燃料元件起泡特性影响数值模拟. 《原子能科学技术》.
284. 韩睿钰，王成龙，郭凯伦，苏光辉，秋穗正，田文喜（2023）. 静默式热管反应堆热工水力特性不确定性分析. 《原子能科学技术》.
285. 金钊，王成龙，代智文，苏光辉，田文喜，秋穗正，包轶颖（2023）. 空间热离子核电源在轨防冻加热策略研究. 《原子能科学技术》.
286. 葛魁，张亚培，田文喜，苏光辉，秋穗正（2023）. 钠冷快堆堆芯熔融物射流碎裂特性理论研究. 《原子能科学技术》.
287. 张鹏辉，卢国庆，陈荣华，许宛清，苏光辉，田文喜，秋穗正（2023）. 可视化交互式核动力系统模拟平台VITARS的开发与验证. 《原子能科学技术》.
288. 李潘潇，张智鹏，代智文，王成龙，田文喜，秋穗正，苏光辉（2023）. 双模式热管堆电热原理样机设计及验证实验研究. 《原子能科学技术》.
289. 陆定晟，魏诗颖，王成龙，田文喜，苏光辉，秋穗正（2023）. 车载运动条件下铅铋堆LESMOR热工安全特性分析. 《原子能科学技术》.
290. 顾晨，贺亚男，邓超群，巫英伟，章静，田文喜，苏光辉，秋穗正（2023）. 基于在线耦合的球形燃料元件温度场计算. 《核动力工程》.
291. 陆定晟，王琛，王成龙，岳倪娜，杨平，田文喜，苏光辉，秋穗正（2023）. 卧式铅铋堆芯氧化腐蚀特性研究. 《核动力工程》.
292. 蔡庆航，陈荣华，肖鑫坤，付浩，田文喜，秋穗正，苏光辉（2023）. 铅基反应堆严重事故下燃料迁徙行为机理实验研究. 《核动力工程》.
293. 李潘潇，张智鹏，王成龙，张大林，秋穗正，苏光辉（2023）. 多用途热管堆原型样机概念设计及堆芯物理分析. 《核动力工程》.
294. Jie Cai, Kun Zhang, L. Chen, Binzhuo Xia, R.H. Chen, Wenxi Tian, Suizheng Qiu (2023). Program development for mass flowrate distribution optimization in the nuclear power plant. Annals of Nuclear Energy.DOI
295. Xindi Lv, Dalin Zhang, Gongle Song, G.H. Su, Wenxi Tian, Suizheng Qiu (2023). Experimental study on flow patterns in narrow rectangular channels. Progress in Nuclear Energy.DOI
296. Wen Ding, Kui Zhang, Ronghua Chen, Wenxi Tian, Jing Zhang, Suizheng Qiu, G.H. Su (2023). Thermo-Physical Property Database of Fusion Materials and Thermo-Hydraulic Database of Breeder Blankets for CFETR. Springer proceedings in physics.DOI
297. Dianqiang Jiang, Dalin Zhang, Kailong Chen, Xinyu Li, Xingguang Zhou, Wenxi Tian, Suizheng Qiu, G.H. Su (2023). EXPERIMENTAL STUDY ON FLOW AND HEAT TRANSFER OF HIGH PRANDTL NUMBER FLUID ALONG HELICAL CRUCIFORM SINGLE ROD. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
298. Xinyu Li, Dalin Zhang, Xingguang Zhou, Xindi Lv, Dianqiang Jiang, Wenxi Tian, Suizheng Qiu, G.H. Su (2023). HIERARCHICAL TWO-TIERED SCALING APPLICATION TO THE HEAT TRANSPORT AND PASSIVE RESIDUAL HEAT REMOVAL SYSTEM OF FLUORIDE-SALT-COOLED HIGHTEMPERATURE ADVANCED REACTOR. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
299. Zheng Junqiang, Yanan He, Junmei Wu, Yingwei Wu, Yuanming Li, Wenxi Tian, Guanghui Su, Suizheng Qiu (2023). THE DEVELOPMENT OF FISSION PRODUCT DIFFUSION/RELEASE MODEL FOR FAILED TRISO PARTICLES. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
300. Dalin Zhang, Xinyu Li, Dianqiang Jiang, Xingguang Zhou, Xindi Lv, Shichang Yun, Wenqiang Wu, Xuanang He, H. B. Li, Xin Min, Kailong Chen, Wenxi Tian, Suizheng Qiu, G.H. Su, Quanbin Zhao, Yao Fu, Chuntao Tang, Wenbin Zhuo, Jinggang Li, Zuo Jiaxu (2023). Fluoride-Salt-cooled high-Temperature Advanced Reactor (FuSTAR): An integrated nuclear-based energy production and conversion system. Energy.DOI
301. Yicong Lan, Yapei Zhang, Wenxi Tian, G.H. Su, Suizheng Qiu (2023). INVESTIGATION ON EX-VESSEL CORIUM SPREADING PROCESS WITH INCOMPRESSIBLE SMOOTHED PARTICLE HYDRODYNAMICS METHOD. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
302. Hao Yao, Yixiang Liao, Yingwei Wu, Suizheng Qiu, G.H. Su, Wenxi Tian (2023). CFD INVESTIGATION ON VORTEX ENTRAINMENT PHENOMENON OF POOL-TYPE SODIUM-COOLED FAST REACTORS. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
303. Ruixiao Zhang, Hongquan Liu, Zhiwei Lü, Yanan He, Yingwei Wu, Wenxi Tian, G.H. Su, Suizheng Qiu (2023). DEVELOPMENT OF AN ANISOTROPIC MECHANICAL MODEL FOR FROBA CODE AND ITS APPLICATIONS FOR SIC COMPOSITE CLADDING ANALYSIS. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
304. Xinyu Li, Dalin Zhang, Xingguang Zhou, Wenxi Tian, Suizheng Qiu (2023). Structure Design and Optimization of the Mass Flow Distribution Device of Downcomer for Fluoride-Salt-Cooled High-Temperature Advanced Reactor – FuSTAR. Springer proceedings in physics.DOI
305. Yapeng Liu, Dalin Zhang, Lei Zhou, Kailong Chen, Wenxi Tian, Suizheng Qiu, G.H. Su (2023). Analysis of the effect of thermal stratification on the natural circulation decay heat removal of sodium-cooled fast reactor. Progress in Nuclear Energy.DOI
306. Yupeng Yang, Chenglong Wang, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2023). DESIGN OPTIMIZATION OF LEAD-BISMUTH HELICAL COIL ONCE-THROUGH TUBE STEAM GENERATOR BASED ON POROUS MEDIUM METHOD. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
307. Kui Ge, Jingyuan Bai, Yapei Zhang, Wenxi Tian, G.H. Su, Suizheng Qiu (2023). TRANSIENT BEHAVIORS OF HEAVY METALLIC LAYER AND EFFECTS OF PR ON THE HEAT TRANSFER CHARACTERISTICS. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
308. Tianzhou Ye, Huan Yao, Yingwei Wu, Jing Zhang, Mingjun Wang, Wenxi Tian, G.H. Su, Suizheng Qiu (2023). EFFECT OF SYMMETRICAL TILT GRAIN BOUNDARIES ON DISPLACEMENT CASCADES IN FE-CR-AL ALLOYS BASED ON ATOMIC SIMULATIONS. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
309. Yichao Ma, Dexiang Kong, Jing Zhang, Mingjun Wang, Yingwei Wu, Wenxi Tian, Suizheng Qiu, G.H. Su (2023). DEVELOPMENT AND EVALUATION OF FLOW REGIME IDENTIFICATION MODEL BASED ON MACHINE LEARNING ALGORITHM. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
310. Jian Yu, Yapei Zhang, G.H. Su, Wenxi Tian, Suizheng Qiu (2023). EXPERIMENTAL STUDY ON THE EFFECT OF NaOH AND Na3PO4 ON SiO2 NANOFLUID SATURATED POOL BOILING CHF. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
311. Haoli Wang, Yapei Zhang, Wenxi Tian, G.H. Su, Suizheng Qiu (2023). PHASE-FIELD MODELING OF MOLTEN ZIRCONIUM OXIDATION COUPLED WITH FLOW AND HEAT TRANSPORT. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
312. Kailin Lu, Yanan He, Yingwei Wu, Jing Zhang, Haoyu Liao, G.H. Su, Suizheng Qiu (2023). MODIFICATION OF FROBA-THERMION AND ITS APPLICATION ON STEADY-STATE PERFORMANCE ANALYSIS OF SINGLE-CELL THERMIONIC FUEL ELEMENTS CONNECTED IN SERIES. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
313. Hongjian Guo, Zhiwen Dai, Jing Zhang, Yingwei Wu, Mingjun Wang, Suizheng Qiu, G.H. Su, Wenxi Tian (2023). ANALYSIS OF FLOW-INDUCED VIBRATION OF WIRE-WRAPPED FUEL BUNDLE CONSIDERING THE EFFECTS OF GEOMETRICAL AND BOUNDARY CONDITIONS. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
314. Shihao Wu, Yapei Zhang, Dong Wang, Kui Ge, Wenxi Tian, G.H. Su, Suizheng Qiu, Songtao Ji, Xiaojun He, Xiao‐Lei Shi (2023). STUDY ON THE DEGRADATION BEHAVIORS OF ANNULAR FUEL UNDER SEVERE ACCIDENT. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
315. Xinyu Li, Dalin Zhang, Shichang Yun, Xingguang Zhou, Dianqiang Jiang, Xindi Lv, Zhenyu Feng, Wenqiang Wu, Wenxi Tian, Suizheng Qiu, G.H. Su, Quanbin Zhao, Xiuting LIU (2023). Design and optimal thermal efficiency contrastive analysis on closed Brayton cycle systems with different fluids of fluoride-salt-cooled high-temperature advanced reactor. Applied Thermal Engineering.DOI
316. Yu Liang, Dalin Zhang, Jing Zhang, Xiao Liu, Yapeng Liu, Lei Zhou, Yutong Chen, Xiaoyu Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2023). A subchannel analysis code SACOS-Na for sodium-cooled fast reactor. Progress in Nuclear Energy.DOI
317. Xingguang Zhou, Dalin Zhang, Xinyu Li, Xindi Lv, Dianqiang Jiang, Wenxi Tian, Suizheng Qiu (2023). Preliminary conceptual design with neutronics and thermal-hydraulics assessments of FuSTAR. Annals of Nuclear Energy.DOI
318. Shihao Wu, Dong Wang, Yapei Zhang, Yukun Zhou, Wenxi Tian, Suizheng Qiu, G.H. Su (2023). Uncertainty analysis of molten corium In-Vessel Retention under External Reactor Vessel Cooling. International Journal of Advanced Nuclear Reactor Design and Technology.DOI
319. Dingsheng Lu, Yupeng Yang, Chenglong Wang, Dalin Zhang, Pengrui Qiao, Wenxi Tian, Suizheng Qiu, G.H. Su (2023). Corrosion effect analysis on thermal-hydraulics of LBE/water spiral tube steam generator under oxygen-controlled environment. Applied Thermal Engineering.DOI
320. Shihao Wu, Dong Wang, Yapei Zhang, Koji Okamoto, Marco Pellegrini, Wenxi Tian, Suizheng Qiu, G.H. Su (2023). Model development for oxidation and degradation behavior of accident tolerant Cr coating on Zr alloy cladding under high temperature steam atmosphere. Journal of Nuclear Materials.DOI
321. Tianzhou Ye, Yingwei Wu, Zetao Wang, Jing Zhang, Mingjun Wang, Ping Chen, Wenxi Tian, G.H. Su, Suizheng Qiu (2023). Simulation of threshold displacement energy in Fe-Cr-Al alloys using molecular dynamics. Journal of Nuclear Materials.DOI
322. Lanfei Yuan, Zhipeng Liu, Chenglong Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2023). Numerical study on thermal-hydraulic characteristics of lead-bismuth loop system under moving conditions. Annals of Nuclear Energy.DOI
323. Rong Zhang, Dalin Zhang, Liang Yu, Jinshun Wang, Jian Deng, Xisi Zhang, Zhixin Niu, Wenxi Tian, Suizheng Qiu, Qi Luo (2023). Subchannel thermal–hydraulic analysis of a wire-wrapped 19-pin rod bundle in the NACIE-UP facility. Annals of Nuclear Energy.DOI
324. Zhengyang Dong, Kai Liu, Mingjun Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2023). The development of nuclear reactor three-dimensional neutronic thermal–hydraulic coupling code: CorTAF-2.0. Nuclear Engineering and Design.DOI
325. Qishi Sun, Ruiyu Han, Kailun Guo, Chenglong Wang, Jing Zhang, Xiaoqiang He, Suizheng Qiu, G.H. Su, Wenxi Tian (2023). Characterization of high-performance nanostructured wick for heat pipes. Applied Thermal Engineering.DOI
326. Chenglong Wang, Yuliang Fang, Wenxi Tian, G.H. Su, Suizheng Qiu (2023). Experimental investigation on heat transfer of nitrogen flowing in a circular tube. Nuclear Engineering and Technology.DOI
327. Zeqin Zhang, Chenglong Wang, Chao Tan, Kailun Guo, Guanghui Su, Wenxi Tian, Suizheng Qiu (2023). Investigation of neutronic and thermal–electric coupling phenomenon in a 100 kWe-level nuclear silent heat pipe-cooled reactor. Applied Thermal Engineering.DOI
328. Qifan Yu, Yafeng Zhao, Yutong Chen, Zhipeng Liu, Chenglong Wang, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2023). Multiphase simulation of hyperbaric steam-water jet inside liquid Pb-Bi eutectic environment. Annals of Nuclear Energy.DOI
329. Z.X. Zhang, Chenglong Wang, Kailun Guo, Wenxi Tian, Suizheng Qiu, G.H. Su (2023). Steady-state multi-physics coupling analysis of heat pipe cooled reactor core. Progress in Nuclear Energy.DOI
330. Lingyi Zhang, Chenglong Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2023). Comparative study of two quick-analysis models for frozen startup of high-temperature heat pipes. Annals of Nuclear Energy.DOI
331. Wen Hua Ding, Kui Zhang, Dalin Zhang, Ronghua Chen, Zhongyun Ju, Caihong Xu, Ting Wang, Wenxi Tian, Suizheng Qiu (2023). Analysis of thermal hydraulic system code LOCUST V1.2 with ECC thermal mixing test facility. International Journal of Advanced Nuclear Reactor Design and Technology.DOI
332. Kui Zhang, Kepiao Li, Xiaofeng Xie, Wenxi Tian, Xing Yu Jiang, Suizheng Qiu (2023). Experimental research on liquid entrainment in the inclined up tee branch. Annals of Nuclear Energy.DOI
333. Lei Zhou, Dalin Zhang, Shibao Wang, Yapeng Liu, Liang Yu, Jing Zhang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2023). Benchmark analysis of the FFTF LOSWOS test #13 with OpenMC and THACS. Annals of Nuclear Energy.DOI
334. Zhiying Yue, Yanan He, Fengrui Xiang, Yingwei Wu, Jing Zhang, Wenxi Tian, G.H. Su, Suizheng Qiu (2023). Coupled neutronics, thermal-hydraulics, and fuel performance analysis of dispersion plate-type fuel assembly in a cohesive way. Nuclear Engineering and Design.DOI
335. Qiang Lian, Simiao Tang, Longxiang Zhu, Luteng Zhang, Wan Sun, Shanshan Bu, Liangming Pan, Wenxi Tian, Suizheng Qiu, G.H. Su, Xinghua Wu, Xiaoyu Wang (2023). Three-dimensional thermal-hydraulics/neutronics coupling analysis on the full-scale module of helium-cooled tritium-breeding blanket. Nuclear Engineering and Technology.DOI
336. Qiang Lian, Simiao Tang, Longxiang Zhu, Luteng Zhang, Wan Sun, Shasha Liu, Shanshan Bu, Liangming Pan, Wenxi Tian, Suizheng Qiu, G.H. Su, Xinghua Wu, Xiaoyu Wang (2023). Structure optimization of helium-cooled blanket for fusion reactor based on three-dimensional full-scale thermal-hydraulic analysis. Fusion Engineering and Design.DOI
337. Wei Li, Hongjian Guo, Jing Zhang, Yingwei Wu, Mingjun Wang, Suizheng Qiu, G.H. Su, Wenxi Tian (2023). Study on the characteristics of axial fluid excitation on fuel rods with spacer grids. Annals of Nuclear Energy.DOI
338. Kai Liu, Mingjun Wang, Jing Zhang, Kailun Guo, Wenxi Tian, Suizheng Qiu, G.H. Su (2023). Numerical investigation on the thermal load heterogeneity of multi-assembly helical coil steam generator in high temperature gas-cooled reactor. Energy.DOI
339. Yupeng Yang, Chenglong Wang, Dalin Zhang, Suizheng Qiu, G.H. Su, Wenxi Tian (2023). Heat transfer evaluation of liquid lead-bismuth eutectic cross flow tube bundle: Experimental part. International Journal of Thermal Sciences.DOI
340. Zetao Wang, Tianzhou Ye, Kailun Guo, Chenglong Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2023). Molecular dynamics simulation of the evaporation of thin liquid sodium film on the conical nanostructure surface. Progress in Nuclear Energy.DOI
341. Zhixing Tian, Chenglong Wang, Kailun Guo, Dalin Zhang, G.H. Su, Wenxi Tian, Suizheng Qiu (2023). A review of liquid metal high temperature heat pipes: Theoretical model, design, and application. International Journal of Heat and Mass Transfer.DOI
342. Qinghang Cai, Ronghua Chen, Kailun Guo, Wenxi Tian, Suizheng Qiu, G.H. Su (2023). An enhanced moving particle semi-implicit method for simulation of incompressible fluid flow and fluid-structure interaction. Computers & Mathematics with Applications.DOI
343. Yupeng Yang, Chenglong Wang, Dalin Zhang, Suizheng Qiu, G.H. Su, Wenxi Tian (2023). Heat transfer evaluation of liquid lead‑bismuth eutectic cross flow tube bundle: Numerical simulation part. International Communications in Heat and Mass Transfer.DOI
344. Xinze Li, Dalin Zhang, Xinyu Li, Wenxi Tian, Suizheng Qiu, G.H. Su (2023). Study on iterative algorithm of full plate cross-flow and counter-flow printed circuit heat exchanger for fluoride-salt-cooled high-temperature advanced reactor. International Journal of Advanced Nuclear Reactor Design and Technology.DOI
345. Zhengyang Dong, Kai Liu, Mingjun Wang, J. Zhang, Jing Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2023). Study on the deposition migration and heat transfer characteristics in the reactor core based on OpenFOAM. Applied Thermal Engineering.DOI
346. Fengrui Xiang, Yanan He, Yingwei Wu, Yuhang Niu, Suizheng Qiu, Changbing Tang, Kunpeng Wang, Wenxi Tian, G.H. Su (2023). Investigation of plate fuel performance under reactivity initiated accidents with developed multi-dimensional coupled method. Journal of Nuclear Materials.DOI
347. Xinyu Li, Dalin Zhang, Xindi Lv, Xingguang Zhou, Wenxi Tian, Suizheng Qiu, G.H. Su (2023). Simulation and design of passive residual heat removal system for Fluoride-Salt-cooled high-Temperature Advanced reactor (FuSTAR). Applied Thermal Engineering.DOI
348. Kun Yue, Chenglong Wang, Ran Zhang, Suizheng Qiu, G.H. Su, Wenxi Tian (2023). Shutdown safety analysis of megawatt-class space gas-cooled reactor system. Progress in Nuclear Energy.DOI
349. Shihao Wu, Yapei Zhang, Dong Wang, Kui Ge, Wenxi Tian, Suizheng Qiu, G.H. Su, Songtao Ji, Xiaojun He, Xiao‐Lei Shi (2023). Experimental and numerical study on the oxidation and melting behaviors of annular fuel rod under high temperature steam condition. Progress in Nuclear Energy.DOI
350. Qifan Yu, Suizheng Qiu, Chenglong Wang, Dalin Zhang, Wenxi Tian, G.H. Su (2023). An experimental review of steam generator tube rupture accident in lead-cooled fast reactors: Thermal-hydraulic experiments classification and methods introduction. Progress in Nuclear Energy.DOI
351. Xitong Liu, Kai Liu, Mingjun Wang, Chong Chen, Qi Lu, Wenxi Tian, Suizheng Qiu, G.H. Su (2023). Three-dimensional thermal-hydraulic characteristics analysis of plate-type fuel reactor core based on OpenFOAM. Progress in Nuclear Energy.DOI
352. Dong Wang, Ruhao Zhong, Yapei Zhang, Peng Chen, Jian Yu, Yicong Lan, G.H. Su, Suizheng Qiu, Wenxi Tian, Yehong Liao, Zhenxun Peng (2023). Oxidation behavior and kinetics of magnetron-sputtered Cr-coated Zr alloy cladding in 1000–1300 ℃ steam environment. Corrosion Science.DOI
353. Chunhui Dong, Shikang Chen, Ronghua Chen, Wenxi Tian, Suizheng Qiu, G.H. Su (2023). Numerical simulation of natural convection around the dome in the passive containment air-cooling system. Nuclear Engineering and Technology.DOI
354. Hao Qin, Carlo Fiorina, Ran Zhang, Stefan Radman, Dalin Zhang, Chenglong Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2023). Extension of GeN-Foam to modeling of boiling water and validation against the OECD/NRC PSBT benchmark. Nuclear Engineering and Design.DOI
355. Xingguang Zhou, Dalin Zhang, Jie Liu, Chao Lin, Liang Yu, Wenxi Tian, Suizheng Qiu, Guanghui Su (2023). Numerical and experimental analysis of LBE flow and heat transfer characteristics in hexagonal rod bundles. Annals of Nuclear Energy.DOI
356. Kailun Guo, Yin Zhang, Xingyang Lin, Jinlu Huang, Chenglong Wang, Suizheng Qiu, Wenxi Tian, Guanghui Su (2023). Transient thermoelectric characteristics of the principle prototype for the heat pipe cooled nuclear Silent themoelectirc reactor (NUSTER). Annals of Nuclear Energy.DOI
357. Chenglong Wang, Siyuan Chen, Wenxi Tian, G.H. Su, Suizheng Qiu (2023). Thermal-hydraulic analysis of He–Xe gas mixture in 2×2 rod bundle wrapped with helical wires. Nuclear Engineering and Technology.DOI
358. Penghui Zhang, Ronghua Chen, G.H. Su, Wenxi Tian, Suizheng Qiu (2023). Experimental investigation and modeling of falling film heat transfer on partial dry-out condition. Applied Thermal Engineering.DOI
359. Yuliang Fang, Qifan Yu, Chenglong Wang, Wenxi Tian, Guanghui Su, Suizheng Qiu (2023). Heat transfer of hydrogen with variable properties in a heated tube. International Journal of Heat and Mass Transfer.DOI
360. Kailun Guo, Sijun Li, Yubao Zhong, Ronghua Chen, Mingjun Wang, Suizheng Qiu, Wenxi Tian, G.H. Su (2023). Heat Transfer Mechanism Investigation of Bubble Growth on the Superhydrophilic Nano-Structured Surface Using Moving Particle Semi-Implicit Method. Applied Sciences.DOI
361. Hongjian Guo, Wei Li, Jing Zhang, Yingwei Wu, Mingjun Wang, Suizheng Qiu, G.H. Su, Wenxi Tian (2023). Analysis of flow-induced vibration of wire-wrapped fuel assemblies under the liquid metal axial flow in the Gen-IV nuclear reactor. Annals of Nuclear Energy.DOI
362. Xingguang Zhou, Dalin Zhang, Xinyu Li, Wenxi Tian, G.H. Su, Suizheng Qiu (2023). High-fidelity neutronics and thermal-hydraulics analysis of helical cruciform fuel based on small modular FHR. Progress in Nuclear Energy.DOI
363. Yanan He, Chen Gu, Chaoqun Deng, Yingwei Wu, G.H. Su, Wenxi Tian, Suizheng Qiu (2023). Development of a hybrid model for fuel performance analysis of spherical fuel elements under normal conditions. Journal of Nuclear Materials.DOI
364. Shihao Wu, Yapei Zhang, Dong Wang, Kui Ge, Wenxi Tian, Suizheng Qiu, G.H. Su (2023). Study on the safety characteristics of molten corium in-vessel retention of annular fuel core. Annals of Nuclear Energy.DOI
365. Qifan Yu, Yuliang Fang, Yafeng Zhao, Suizheng Qiu, Chenglong Wang, Dalin Zhang, Wenxi Tian, G.H. Su (2023). Experimental investigation of pressure fluctuation and steam transport under SGTR accident in Lead-cooled Fast Reactors. International Journal of Heat and Mass Transfer.DOI
366. Zetao Wang, Tianzhou Ye, Kailun Guo, Wenxi Tian, Suizheng Qiu, G.H. Su (2023). The evaporation of nanoscale sodium liquid film on the non-ideal nanostructure surface: A molecular dynamics study. International Journal of Advanced Nuclear Reactor Design and Technology.DOI
367. Liangguo Li, Jianming Yu, Zongbao Nan, Donghua Lu, Jun Xing, Xianghui Lu, Yingwei Wu, Suizheng Qiu, Guanghui Su, Wenxi Tian, Xiaohang Wu, Jiyong Liu (2023). Experimental research and theoretical analysis of flow instability in advanced secondary passive residual heat removal system. Annals of Nuclear Energy.DOI
368. Kai Liu, Mingjun Wang, Wenxi Tian, Jing Zhang, Suizheng Qiu, G.H. Su (2023). CorTAF: A nuclear reactor core three-dimensional thermal-hydraulic characteristics analysis code based on OpenFOAM. Nuclear Engineering and Design.DOI
369. Zetao Wang, Tianzhou Ye, Kailun Guo, Wenxi Tian, Suizheng Qiu, G.H. Su (2023). Molecular dynamics study of the wettability effect on the evaporation of thin liquid sodium film. Nuclear Engineering and Design.DOI
370. Shichang Yun, Dalin Zhang, Xinyu Li, Xingguang Zhou, Dianqiang Jiang, Xindi Lv, Wenqiang Wu, Zhenyu Feng, Xin Min, Wenxi Tian, Suizheng Qiu, G.H. Su (2023). Design, optimization and thermodynamic analysis of SCO2 Brayton cycle system for FHR. Progress in Nuclear Energy.DOI
371. Shichang Yun, Dalin Zhang, Xinyu Li, Xuanang He, Wenxi Tian, Suizheng Qiu, G.H. Su, Quanbin Zhao (2023). Superstructure design and optimization on closed Brayton cycle system of fluoride-salt-cooled high-temperature advanced reactor. Applied Energy.DOI
372. Huang Jinlu, Tian Zhixing, Wang Chenglong, Guo Kailun, Zhang Dalin, Tian Wenxi, Qiu Suizheng, Su Guanghui (2023). TRANSIENT THERMAL SAFETY ANALYSIS OF NUSTER-100 REACTOR CORE. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
373. Dexiang Kong, Yichao Ma, Jing Zhang, Wang Mingjun, Wu Yingwei, Su Guanghui, Qiu Suizheng, Tian Wenxi (2023). RESEARCH ON CHF MODEL BASED ON DEEP LEARNING ALGORITHM. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
374. Tian Zhixing, Wang Chenglong, Zhang Jiarui, Huang Jinlu, Guo Kailun, Zhang Dalin, Tian Wenxi, Qiu Suizheng, Su Guanghui (2023). DEVELOPMENT OF SODIUM HEAT PIPES FOR NUCLEAR SILENT THERMALELECTRICAL REACTOR (NUSTER-100). The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
375. 陈荣华，田文喜，苏光辉，秋穗正（2022）. 工程分析程序设计“线上+线下”教学新模式的探索与实践. 《大学教育》.
376. 房玉良，王成龙，田文喜，苏光辉，秋穗正（2022）. 100kN核热推进系统方案热工设计分析. 《第六届空天动力联合会议暨中国航天第三专业信息网第四十二届技术交流会暨2021航空发动机技术发展高层论坛论文集（第六册）》.DOI
377. 田智星，王成龙，郭凯伦，张大林，田文喜，秋穗正，苏光辉（2022）. 不凝气体对高温钠热管启动及稳态热性能影响的实验研究. 《第六届空天动力联合会议暨中国航天第三专业信息网第四十二届技术交流会暨2021航空发动机技术发展高层论坛论文集（第六册）》.DOI
378. 孙洪平，邓坚，罗跃建，张明，许幼幼，武小莉，刘丽莉，陈冲，秋穗正，苏光辉（2022）. 池式钠火事故下燃烧产物气溶胶行为研究. 《核动力工程》.
379. 田智星，王成龙，郭凯伦，张大林，田文喜，秋穗正，苏光辉（2022）. 热管堆用高温热管参数敏感性分析和优化. 《核动力工程》.
380. 郑军强，贺亚男，章静，巫英伟，田文喜，苏光辉，秋穗正（2022）. TRISO包覆燃料颗粒裂变产物扩散释放特性研究. 《核动力工程》.
381. 曾春杰，王明军，田文喜，秋穗正，苏光辉（2022）. 蒸汽发生器全尺寸汽水分离装置模型开发. 《原子能科学技术》.
382. 田文喜，王明军，曾春杰，秋穗正，苏光辉（2022）. 核动力蒸汽发生器三维热工水力分析程序STAF的发展与应用. 《原子能科学技术》.
383. 金钊，王成龙，田文喜，秋穗正，苏光辉（2022）. 空间热离子反应堆在轨保温策略及分析. 《原子能科学技术》.
384. 焦拥军，李正阳，蒲曾坪，任全耀，郑美银，巫英伟，秋穗正（2022）. 锆合金包壳在微动磨蚀环境下的界面损伤行为. 《中国表面工程》.
385. 刘凯，王明军，田文喜，秋穗正，苏光辉（2022）. 数值反应堆堆芯通道级三维热工水力程序CorTAF开发及初步验证. 《原子能科学技术》.
386. 周磊，张大林，刘雅鹏，王式保，王心安，王成龙，田文喜，秋穗正，苏光辉（2022）. 快中子通量实验堆失流事故三维数值模拟. 《原子能科学技术》.
387. 金钊，王成龙，刘逍，代智文，田文喜，秋穗正，苏光辉（2022）. 百千瓦级空间锂冷快堆系统热工安全特性研究. 《原子能科学技术》.
388. 吴志远，张魁，冯唐涛，陈荣华，田文喜，秋穗正，苏光辉（2022）. 基于替代材料的燃料棒熔化实验研究. 《原子能科学技术》.
389. 汪泽涛，郭凯伦，王成龙，张大林，田文喜，秋穗正，苏光辉（2022）. 钠热管中气液交界质量调节系数的分子动力学研究. 《原子能科学技术》.
390. 肖鑫坤，蔡庆航，陈荣华，丁雯，张魁，郭凯伦，田文喜，秋穗正，苏光辉（2022）. 基于MPS方法的离散固体与流体相互作用数值模拟研究. 《原子能科学技术》.
391. 张明昊，王成龙，田智星，郭凯伦，田文喜，苏光辉，秋穗正（2022）. 不凝性气体对高温锂热管传热特性的影响研究. 《原子能科学技术》.
392. 岳坤，王成龙，张冉，秋穗正，苏光辉，田文喜（2022）. 兆瓦级空间气冷堆系统启停堆瞬态分析. 《原子能科学技术》.
393. 韩梓超，章静，王明军，田文喜，苏光辉，秋穗正（2022）. 核热推进系统氢气物性及流动换热模型分析. 《原子能科学技术》.
394. 温永江，王成龙，张大林，秋穗正，苏光辉，田文喜（2022）. 核热推进反应堆外环境辐射场研究. 《原子能科学技术》.
395. 马翊超，尹莎莎，章静，田文喜，秋穗正，苏光辉（2022）. 静止和摇摆条件下浮动式核电站一二回路PRHRS特性分析. 《原子能科学技术》.
396. 秋穗正，张泽秦，张智鹏，王成龙，郭凯伦，田文喜，苏光辉（2022）. 海洋静默式热管反应堆热工水力特性研究. 《原子能科学技术》.
397. 汪泽涛，郭凯伦，王成龙，张大林，田文喜，秋穗正，苏光辉（2022）. 高温热管内钠蒸发冷凝特性分子动力学研究. 《原子能科学技术》.
398. 丁雯，张大林，张魁，陈荣华，谢晓风，琚忠云，徐财红，王婷，田文喜，秋穗正（2022）. 基于ECC安注热混合试验的LOCUST 1.2分析与验证. 《原子能科学技术》.
399. 张智鹏，杨浩然，王海平，步珊珊，王成龙，田文喜，苏光辉，张大林，秋穗正（2022）. 兆瓦级热管反应堆堆芯核热特性研究. 《原子能科学技术》.
400. 张胤，郭凯伦，王成龙，戴春辉，宋苹，张大林，秋穗正，田文喜，苏光辉（2022）. 热管堆中分段式温差发电器的仿真分析. 《原子能科学技术》.
401. 刘凯，李林峰，王明军，章静，田文喜，秋穗正，苏光辉（2022）. 基于CFD方法的矩形窄缝通道内过冷流动沸腾模型研究. 《原子能科学技术》.
402. 张嘉睿，田智星，王成龙，田文喜，郭凯伦，秋穗正，苏光辉（2022）. 液态金属高温热管传热极限研究. 《原子能科学技术》.
403. 于启帆，赵亚峰，王成龙，张大林，田文喜，秋穗正，苏光辉（2022）. 铅基快堆SGTR事故下热工水力模拟及气腔扩散行为研究. 《原子能科学技术》.
404. 朱志明，李可飘，张魁，田文喜，陈荣华，秋穗正（2022）. 运动条件螺旋管内流动换热特性研究. 《原子能科学技术》.
405. 穆德芳，王明军，田文喜，秋穗正，苏光辉（2022）. 蒸汽发生器支承板杂质沉积及堵塞数值模拟研究. 《原子能科学技术》.
406. 刘凯，王明军，章静，田文喜，秋穗正，苏光辉（2022）. 螺旋管蒸汽发生器三维热工水力程序HeTAF开发. 《原子能科学技术》.
407. 王明军，孙金象，章静，田文喜，秋穗正，苏光辉（2022）. 高温气冷堆螺旋管蒸汽发生器热工水力特性研究. 《原子能科学技术》.
408. 田智星，刘余，王成龙，郭凯伦，张大林，田文喜，秋穗正，苏光辉（2022）. 高温热管传热传质数值模型研究综述. 《核科学与工程》.
409. 陈静，秋穗正，王明军，黄鹏（2022）. VVER型反应堆上腔室及热腿三维流动传热特性研究. 《核科学与工程》.
410. 王莹杰，王明军，王树强，田文喜，秋穗正，苏光辉（2022）. 核动力系统蒸汽发生器U形管流致振动数值模拟. 《核科学与工程》.
411. Yandong Hou, Liu Wang, Kui Zhang, Mingjun Wang, Yingwei Wu, Wenxi Tian, Suizheng Qiu, G.H. Su (2022). Experimental study on boiling two-phase of liquid sodium along a 7-rod bundle – Part Ⅰ: Pressure drop characteristics. Annals of Nuclear Energy.DOI
412. Yandong Hou, Liu Wang, Kui Zhang, Mingjun Wang, Yingwei Wu, Wenxi Tian, Suizheng Qiu, G.H. Su (2022). Experimental study on boiling two-phase of liquid sodium along a 7-rod bundle – Part Ⅱ: Heat transfer characteristics. Annals of Nuclear Energy.DOI
413. Dianqiang Jiang, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2022). Numerical study on transverse mixing characteristics of flow sweeping in helical cruciform rod bundle. Applied Thermal Engineering.DOI
414. Yi Liao, Qi Cai, Shaopeng He, Mingjun Wang, Hongguang Xiao, Zili Gong, Cong Wang, Zhen Jia, Tangtao Feng, Suizheng Qiu (2022). Study on three-dimensional numerical simulation of shell and tube heat exchanger of the surface ship under marine conditions. Nuclear Engineering and Technology.DOI
415. Tianzhou Ye, Zetao Wang, Yingwei Wu, Jing Zhang, Ping Chen, Mingjun Wang, Wenxi Tian, G.H. Su, Suizheng Qiu (2022). Molecular dynamics simulation of tensile deformation behavior of single-crystal Fe–Cr–Al before and after irradiation. Journal of materials research/Pratt's guide to venture capital sources.DOI
416. Dingsheng Lu, Chen Wang, Chen Wang, Chenglong Wang, Chenglong Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2022). Numerical simulation of corrosion phenomena in oxygen-controlled environment for a horizontal lead-bismuth reactor core. Journal of Nuclear Materials.DOI
417. Kui Ge, Yapei Zhang, Kui Zhang, Wenxi Tian, G.H. Su, Suizheng Qiu (2022). Melting and relocation behavior of metal and force balance analysis of metallic droplet. International Journal of Advanced Nuclear Reactor Design and Technology.DOI
418. Ruiyu Han, Zetao Wang, Kailun Guo, Chenglong Wang, Dalin Zhang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2022). Experimental investigation of nano-particle deposited wick Structure's heat transfer characteristics. International Journal of Advanced Nuclear Reactor Design and Technology.DOI
419. Yicong Lan, Yapei Zhang, Wenxi Tian, G.H. Su, Suizheng Qiu (2022). An enhanced implicit viscosity ISPH method for simulating free-surface flow coupled with solid-liquid phase change. Journal of Computational Physics.DOI
420. Kailin Lu, Hao Yao, Yanan He, Yingwei Wu, Jing Zhang, Haoyu Liao, G.H. Su, Suizheng Qiu (2022). Thermionic conversion performance analysis of the single-cell thermionic fuel element based on FROBA-THERMION code. Annals of Nuclear Energy.DOI
421. Zhipeng Liu, Yafeng Zhao, Wenxi Tian, Chenglong Wang, Suizheng Qiu, G.H. Su (2022). Flow fluctuations and flow friction characteristics of lead-bismuth eutectic in a vertical tube under rolling conditions. Annals of Nuclear Energy.DOI
422. Chunhui Dong, Guoqing Lu, Ronghua Chen, Kui Zhang, Changliang Liu, Wenxi Tian, Suizheng Qiu, G.H. Su (2022). Experimental study on turbulent natural convection of air between the open-ended parallel plates with one-side heating. Annals of Nuclear Energy.DOI
423. Wen Jiang Ding, Ronghua Chen, Wenxi Tian, Suizheng Qiu, G.H. Su (2022). Numerical investigation of dynamic characteristics of debris bed formation based on CFD-DEM method. Annals of Nuclear Energy.DOI
424. Zhipeng Liu, Yafeng Zhao, Chenglong Wang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2022). Experimental study on heat transfer characteristics of LBE flow in a vertical tube under static and rolling conditions. International Journal of Heat and Mass Transfer.DOI
425. Chao Xu, Wei Sun, Yusheng Liu, Jian Hu, Suizheng Qiu (2022). Analysis on the results of CAP1400 passive containment cooling system during LOCA scenario via integral test. Progress in Nuclear Energy.DOI
426. Hao Sun, Marco Pellegrini, Chenglong Wang, Shunichi Suzuki, Koji Okamoto, Wenxi Tian, Suizheng Qiu, Guanghui Su (2022). CFD simulation based on film model of high temperature potassium heat pipe at different positions: Horizontal, vertical, and 45° inclined. Progress in Nuclear Energy.DOI
427. Yihu Wang, Meiyin Zheng, Jing Zhang, Yongjun Jiao, Yingwei Wu, Wenxi Tian, G.H. Su, Suizheng Qiu (2022). Numerical simulation study on the fluid excitation force on a nuclear fuel rod with a spacer grid. Annals of Nuclear Energy.DOI
428. Jinlu Huang, Chenglong Wang, Wenxi Tian, Kailun Guo, G.H. Su, Wenxi Tian, Youqi Zheng, Suizheng Qiu (2022). Preliminary conceptual design and analysis of a 100 kW e level Nuclear Silent Thermal‐Electrical Reactor ( NUSTER ‐100). International Journal of Energy Research.DOI
429. Kui Ge, Yapei Zhang, Haoli Wang, Chuanxu Zhang, Wenxi Tian, G.H. Su, Suizheng Qiu, Chang‐Jiang Yang (2022). Development of a PCCS module in the ATHROC for simulation of passive containment cooling system. Progress in Nuclear Energy.DOI
430. Shaopeng He, Mingjun Wang, Jing Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2022). A deep-learning reduced-order model for thermal hydraulic characteristics rapid estimation of steam generators. International Journal of Heat and Mass Transfer.DOI
431. Qinghang Cai, Ronghua Chen, Yonglin Li, Kailun Guo, Wenxi Tian, Suizheng Qiu, G.H. Su (2022). The stability criterion based on the spurious pressure oscillation analysis of MPS method. Annals of Nuclear Energy.DOI
432. Chenglong Wang, Shiying Wei, Wenxi Tian, Suizheng Qiu, G.H. Su (2022). Retraction notice to “Core design and analysis of a lead-bismuth cooled small modular reactor” [Ann. Nucl. Energy 133 (2019) 511–518/6850]. Annals of Nuclear Energy.DOI
433. Jinxiang Sun, Ruibo Zhang, Mingjun Wang, Jing Zhang, Suizheng Qiu, Wenxi Tian, G.H. Su (2022). Multi-objective optimization of helical coil steam generator in high temperature gas reactors with genetic algorithm and response surface method. Energy.DOI
434. Tingjun Yang, Kun Zhang, Wenxi Tian, Siyang Huang, Xinli Gao, R.H. Chen, Suizheng Qiu (2022). Analysis of CHF characteristics with fuel rods in the natural circulation system under motion conditions. Progress in Nuclear Energy.DOI
435. Yapei Zhang, Dekui Zhan, Jingyuan Bai, Simin Luo, Yongkang Li, Wenxi Tian, G.H. Su, Suizheng Qiu, Peng Chen (2022). An investigation of characteristics of flow and heat transfer in the two-layer molten pool under swing motion condition. Progress in Nuclear Energy.DOI
436. Hongquan Liu, Yanan He, Yingwei Wu, Guanghui Su, Wenxi Tian, Suizheng Qiu (2022). Preliminary Development of a Coupling Environment Based on MOOSE and OpenFOAM and Its Application on Plate Fuel Modeling. Volume 15: Student Paper Competition.DOI
437. Tairan Yang, Kun Zhang, Haiyan Yang, Wenxi Tian, Suizheng Qiu (2022). Preliminary study on FROBA-SCO2 with transient models and its application for Reactivity Initiated Accident and loss of flow accident. International Journal of Advanced Nuclear Reactor Design and Technology.DOI
438. Hao Yao, Fengrui Xiang, Yingwei Wu, G.H. Su, Wenxi Tian, Suizheng Qiu (2022). Study on criteria and prediction method of liquid fall type gas entrainment in pool-type sodium-cooled fast reactors. Annals of Nuclear Energy.DOI
439. Linyi Yang, Chenglong Wang, Hao Qin, Dalin Zhang, Wenxi Tian, G.H. Su, Suizheng Qiu (2022). Numerical investigation on radiative and evaporative characteristics of a liquid droplet radiator through Monte-Carlo method. Applied Thermal Engineering.DOI
440. Dong Wang, Ruhao Zhong, Yapei Zhang, Peng Chen, Yicong Lan, Jian Yu, G.H. Su, Suizheng Qiu, Wenxi Tian (2022). Isothermal experiments on steam oxidation of magnetron-sputtered chromium-coated zirconium alloy cladding at 1200 ℃. Corrosion Science.DOI
441. Wenxi Tian, Yu Liu, Chenglong Wang, Kailun Guo, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2022). Single/ multi‐objective optimization and comparative analysis of liquid‐metal heat pipe. International Journal of Energy Research.DOI
442. Tairan Yang, K. Zhang, Wei Tian, Xing Yu Jiang, Xinli Gao, R.H. Chen, Suizheng Qiu (2022). Numerical investigation on heat transfer and pressure drop characteristics of moisture separator reheater with porous media method. Annals of Nuclear Energy.DOI
443. Xinkun Xiao, Qinghang Cai, Ronghua Chen, Wen Jiang Ding, Kailun Guo, Kui Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2022). An improved MPS-DEM numerical model for fluid–solid coupling problem in nuclear reactor. Nuclear Engineering and Design.DOI
444. Chunjie Zeng, Mingjun Wang, Ge Ping Wu, Shasha Yin, Wenxi Tian, Suizheng Qiu, Guanghui Su (2022). Numerical study on the enhanced heat transfer characteristics of steam generator with axial economizer. International Journal of Thermal Sciences.DOI
445. Chunhui Dong, Guoqing Lu, Ronghua Chen, Kui Zhang, Changliang Liu, Wenxi Tian, Suizheng Qiu, G.H. Su (2022). Heat transfer of air turbulent mixed convection in the passive containment air-cooling system of a modular small nuclear reactor. International Journal of Thermal Sciences.DOI
446. Yuhang Niu, Yanan He, Bowen Qiu, Fengrui Xiang, Chaoqun Deng, Yuanming Li, Jing Zhang, Yingwei Wu, Wenxi Tian, G.H. Su, Suizheng Qiu (2022). An effective method for modeling 1D two-phase two-fluid six-equation model with automatic differentiation approach. Progress in Nuclear Energy.DOI
447. Mingjun Wang, Linfeng Li, Kai Liu, Jing Zhang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2022). Development of subcooled wall boiling model considering bubble sliding in narrow rectangular channel. International Journal of Thermal Sciences.DOI
448. Yingjie Wang, Mingjun Wang, Jia Kang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2022). Thermal fatigue analysis of structures subjected to liquid metal jets at different temperatures in the Gen-IV nuclear energy system. Energy.DOI
449. Penghui Zhang, Bowei Wang, Ronghua Chen, G.H. Su, Wenxi Tian, Suizheng Qiu (2022). Water film covering characteristic on horizontal fuel rod under impinging cooling condition. Nuclear Engineering and Technology.DOI
450. Zhichao Wu, Kun Zhang, Tangtao Feng, Yonglin Li, R.H. Chen, Wenxi Tian, G.H. Su, Suizheng Qiu (2022). Experimental study on fuel rod melting based on alternative materials. Annals of Nuclear Energy.DOI
451. Liangpeng Wu, Ruiyu Sun, Ronghua Chen, Wenxi Tian, Suizheng Qiu, G.H. Su (2022). Probability analysis of ex-vessel steam explosion induced pressure load based on analysis code SEINA. Annals of Nuclear Energy.DOI
452. Wen Jiang Ding, Xinkun Xiao, Qinghang Cai, Ronghua Chen, Kailun Guo, Wenxi Tian, Suizheng Qiu, G.H. Su (2022). Numerical investigation of fluid–solid interaction during debris bed formation based on MPS-DEM. Annals of Nuclear Energy.DOI
453. Suizheng Qiu (2022). Study on Thermal-hydraulic Characteristics of Ocean Silent Heat Pipe Cooled Reactor. DOAJ (DOAJ: Directory of Open Access Journals).
454. Kun Zhang, Tingjun Yang, Wenxi Tian, Siyang Huang, Dan Mao, Zeqin Zhang, R.H. Chen, Suizheng Qiu (2022). Analysis of the natural circulation system characteristics with fuel rods under motion conditions. Annals of Nuclear Energy.DOI
455. Kailin Lu, Haoyu Liao, Yanan He, Yingwei Wu, Jing Zhang, Hao Yao, G.H. Su, Suizheng Qiu (2022). Modification of FROBA code and its application in Thermal-Mechanical analysis of the Single-Cell thermionic fuel element. Annals of Nuclear Energy.DOI
456. Kui Ge, Yukun Zhou, Yapei Zhang, Shihao Wu, Wenxi Tian, G.H. Su, Suizheng Qiu (2022). Transient behavior and maximum heat flux ratios of two-layer corium pool. International Journal of Thermal Sciences.DOI
457. Yanan He, Yuhang Niu, Fengrui Xiang, Yingwei Wu, Jing Zhang, G.H. Su, Wenxi Tian, Suizheng Qiu (2022). Preliminary development of a multi-physics coupled fuel performance code for annular fuel analysis under normal conditions. Nuclear Engineering and Design.DOI
458. Chaoqun Deng, Yanan He, Fengrui Xiang, Yingwei Wu, Jing Zhang, Wenxi Tian, G.H. Su, Suizheng Qiu (2022). Finite element based fuel performance investigation of U3Si2–FeCrAl design under normal and RIA conditions. Progress in Nuclear Energy.DOI
459. Shaopeng He, Mingjun Wang, Yandong Hou, Wenxi Tian, Suizheng Qiu, G.H. Su (2022). Study on the flow and heat transfer characteristics of liquid sodium in a hexagonal 7-rod bundle. Nuclear Engineering and Design.DOI
460. Zeqin Zhang, Chenglong Wang, Kailun Guo, Jinlu Huang, Suizheng Qiu, G.H. Su, Wenxi Tian (2022). HEART, a specific code for thermal-electrical analysis of heat pipe cooled nuclear reactor. International Journal of Thermal Sciences.DOI
461. Zhengyang Dong, Hanrui Qiu, Mingjun Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2022). Numerical simulation on the thermal stratification in the lead pool of lead-cooled fast reactor (LFR). Annals of Nuclear Energy.DOI
462. Liangpeng Wu, Ruiyu Sun, Ronghua Chen, Wenxi Tian, Suizheng Qiu, G.H. Su (2022). SEINA: A two-dimensional steam explosion integrated analysis code. Nuclear Engineering and Technology.DOI
463. Haiwang Yang, Chenglong Wang, Kailun Guo, Wenxi Tian, Suizheng Qiu, G.H. Su (2022). WITHDRAWN: Experimental study on thermoelectric characteristics of heat pipe reactor (NUSTER-100) Single Assembly. International Journal of Advanced Nuclear Reactor Design and Technology.DOI
464. Hao Qin, Chenglong Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2022). Experimental investigation on flow and heat transfer characteristics of He-Xe gas mixture. International Journal of Heat and Mass Transfer.DOI
465. Yuliang Fang, Chenglong Wang, Wenxi Tian, Dalin Zhang, Guanghui Su, Suizheng Qiu (2022). Study on high-temperature hydrogen dissociation for nuclear thermal propulsion reactor. Nuclear Engineering and Design.DOI
466. Chenglong Wang, Zhipeng Zhang, Minghao Zhang, Panxiao Li, Zhixing Tian, Wenxi Tian, Suizheng Qiu, G.H. Su (2022). Numerical evaluation of non-condensable gas influence on the heat transfer characteristics of high-temperature lithium heat pipe during reactor operation. Annals of Nuclear Energy.DOI
467. Defang Mu, Mingjun Wang, Jing Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2022). Migration–deposition coupling characteristics and influence of corrosion products on heat transfer in steam generators. Applied Thermal Engineering.DOI
468. Ji Zhang, Nuo Chen, Mingjun Wang, Wenxi Tian, Jing Zhang, Suizheng Qiu, G.H. Su (2022). The fouling and thermal hydraulic coupling study on the typical 5 × 5 rod bundle in PWRs. Progress in Nuclear Energy.DOI
469. Naveed Muhammad, Mingjun Wang, Wenxi Tian, G.H. Su, Suizheng Qiu (2022). LES study on the turbulent thermal stratification and thermo-mechanical fatigue analysis for NPP surge line. International Journal of Thermal Sciences.DOI
470. Haiwang Yang, Chenglong Wang, Dalin Zhang, Jing Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2022). Parameter sensitivity study on startup characteristics of high temperature potassium heat pipe. Nuclear Engineering and Design.DOI
471. Chuanming Zhang, Lianfa Wang, Mingjun Wang, Tingting Xu, Arnaud Barthet, Yinli Liu, Wenxi Tian, Suizheng Qiu, G.H. Su (2022). Numerical simulation of pressure force for control rod guide tube in PWR. Progress in Nuclear Energy.DOI
472. Shaopeng He, Mingjun Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2022). Development of an OpenFOAM solver for numerical simulations of shell-and-tube heat exchangers based on porous media model. Applied Thermal Engineering.DOI
473. Dianqiang Jiang, Dalin Zhang, Xinyu Li, Shibao Wang, Chenglong Wang, Hao Qin, Yanwen Guo, Wenxi Tian, G.H. Su, Suizheng Qiu (2022). Fluoride-salt-cooled high-temperature reactors: Review of historical milestones, research status, challenges, and outlook. Renewable and Sustainable Energy Reviews.DOI
474. Wenxi Tian, Jiarui Zhang, Chenglong Wang, Kailun Guo, Yu Liu, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2022). Experimental evaluation on heat transfer limits of sodium heat pipe with screen mesh for nuclear reactor system. Applied Thermal Engineering.DOI
475. Xin Min, Dalin Zhang, Rongshuan Xu, Shibao Wang, Youchun Chen, Chenglong Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2022). Study on startup characteristics of prototype once-through steam generator for China fast reactor. International Journal of Advanced Nuclear Reactor Design and Technology.DOI
476. Jinlu Huang, Chenglong Wang, Kailun Guo, Dalin Zhang, G.H. Su, Wenxi Tian, Suizheng Qiu (2022). Heat transfer analysis of heat pipe cooled device with thermoelectric generator for nuclear power application. Nuclear Engineering and Design.DOI
477. Y.P. Zhang, Di Zhu, Kui Ge, Yingwei Wu, Wenxi Tian, G.H. Su, Suizheng Qiu (2022). Heat transfer characteristics of single-layer and two-layer corium pool in elliptical lower head. International Journal of Advanced Nuclear Reactor Design and Technology.DOI
478. Zetao Wang, Kailun Guo, Chenglong Wang, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2022). Molecular dynamics study of liquid sodium film evaporation and condensation by Lennard-Jones potential. Nuclear Engineering and Technology.DOI
479. Zetao Wang, Ruiyu Han, Kailun Guo, Chenglong Wang, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2022). Molecular dynamics simulation of the evaporation of liquid sodium film in the presence of non-condensable gas. Annals of Nuclear Energy.DOI
480. Yin Zhang, Xiaoming Chai, Chenglong Wang, Simiao Tang, Dalin Zhang, Wenxi Tian, G.H. Su, Suizheng Qiu (2022). Thermal-hydraulic analysis of heat pipe reactor experimental device with thermoelectric generators. Progress in Nuclear Energy.DOI
481. Jie Liu, Ping Song, Dalin Zhang, Shibao Wang, Chao Lin, Yapeng Liu, Lei Zhou, Chenglong Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2022). Thermal-hydraulic research on rod bundle in the LBE fast reactor with grid spacer. Nuclear Engineering and Technology.DOI
482. Dong Wang, Yapei Zhang, Shihao Wu, G.H. Su, Suizheng Qiu, Wenxi Tian, Yingwei Wu (2022). Development of oxidation model for zirconium alloy cladding and application in the analysis of cladding behavior under loss of coolant accident. Journal of Nuclear Materials.DOI
483. Zhixian Lai, Wenxi Tian, Chong Chen, Mingjun Wang, Kui Zhang, Suizheng Qiu, G.H. Su (2022). Experimental study on thermal hydraulic characteristics of natural circulation loop under motion condition. Applied Thermal Engineering.DOI
484. 黄金露，王成龙，郭凯伦，田文喜，苏光辉，秋穗正（2021）. 新型海洋静默式热管反应堆的概念设计. 《中国基础科学》.
485. 田智星，王成龙，黄金露，张嘉睿，郭凯伦，张大林，田文喜，秋穗正，苏光辉（2021）. 热管冷却反应堆中高温钠热管传热极限实验研究. 《中国核科学技术进展报告（第七卷）——中国核学会2021年学术年会论文集第2册（核能动力分卷）》.DOI
486. 黄金露，王成龙，郭凯伦，田文喜，苏光辉，秋穗正（2021）. 新型海洋静默式热管反应堆（NUSTER-100）电源系统概念设计和分析. 《中国核科学技术进展报告（第七卷）——中国核学会2021年学术年会论文集第2册（核能动力分卷）》.DOI
487. 何少鹏，王明军，章静，田文喜，苏光辉，秋穗正（2021）. 基于OpenFOAM的液态金属铅铋三维流动换热特性数值模拟研究. 《原子能科学技术》.
488. 向烽瑞，牛钰航，邓超群，贺亚男，巫英伟，田文喜，秋穗正，苏光辉（2021）. 基于多物理场耦合方法的板状燃料元件性能分析. 《中国核科学技术进展报告（第七卷）——中国核学会2021年学术年会论文集第2册（核能动力分卷）》.DOI
489. 杨宇鹏，王成龙，张大林，苏光辉，田文喜，秋穗正（2021）. 液态金属螺旋管式直流蒸汽发生器数值模拟研究. 《原子能科学技术》.
490. 张胤，王成龙，唐思邈，李建，张大林，秋穗正，田文喜，苏光辉（2021）. 固态热管反应堆模拟装置热工水力特性分析. 《原子能科学技术》.
491. 王琛，王成龙，张衍，张大林，田文喜，秋穗正，苏光辉（2021）. 液态铅铋合金管内流动传热特性研究. 《原子能科学技术》.
492. 王明军，鞠浩然，赵民富，李伟卿，刘天才，胡长军，杨文，田文喜，秋穗正，苏光辉（2021）. 数值堆热工流体程序CVR-PACA验证及典型应用. 《原子能科学技术》.
493. 房玉良，王成龙，田文喜，苏光辉，秋穗正（2021）. 高温氢工质热物理性质计算分析. 《原子能科学技术》.
494. 邓超群，向烽瑞，贺亚男，牛钰航，巫英伟，田文喜，秋穗正，苏光辉（2021）. 基于MOOSE平台的棒状燃料元件性能瞬态分析程序开发与验证. 《原子能科学技术》.
495. 郭凯伦，王成龙，张大林，秋穗正，苏光辉，田文喜（2021）. 纳米多孔超亲水不锈钢席型网毛细力特性研究. 《核动力工程》.
496. 牛钰航，贺亚男，巫英伟，向烽瑞，邓超群，于洋，苏光辉，秋穗正，田文喜，卢忝余（2021）. 基于MOOSE平台的高阶全隐式核反应堆一回路系统分析. 《核动力工程》.
497. 刘明皓，王成龙，张大林，秋穗正，张玉龙（2021）. 熔盐堆热管式非能动余热排出系统瞬态分析研究. 《核科学与工程》.
498. 牛钰航，芦韡，贺亚男，邓超群，向烽瑞，巫英伟，苏光辉，秋穗正，田文喜，于洋，卢忝余（2021）. 基于MOOSE框架的五方程两相流分析程序开发. 《原子能科学技术》.
499. 刘志鹏，王成龙，张大林，田文喜，秋穗正，苏光辉（2021）. 运动条件下铅铋反应堆热工水力特性研究. 《原子能科学技术》.
500. 段倩妮，王成龙，张大林，秋穗正，苏光辉，田文喜，徐建军（2021）. 余热排出系统中的热管设计及传热性能研究. 《原子能科学技术》.
501. 杨林翼，秦浩，王成龙，张大林，苏光辉，田文喜，秋穗正（2021）. 高温液滴流辐射换热及蒸发特性. 《原子能科学技术》.
502. 张家心，王成龙，赵寒冰，张大林，苏光辉，秋穗正，田文喜（2021）. RELAP5铅铋快堆模型拓展及验证. 《原子能科学技术》.
503. 张明昊，王成龙，孙浩，代智文，张大林，田文喜，秋穗正，苏光辉（2021）. 辐照条件下高温锂热管不凝性气体产生特性研究. 《原子能科学技术》.
504. 陈思远，秦浩，王成龙，张亚培，张大林，秋穗正，田文喜，苏光辉（2021）. 绕丝结构对氦氙气体流动换热特性影响研究. 《原子能科学技术》.
505. 葛魁，王辉，王明军，田文喜，苏光辉，秋穗正（2021）. 华龙一号非能动安全壳热量导出系统热工水力特性研究. 《原子能科学技术》.
506. 张泽秦，王成龙，孙浩，张大林，秋穗正，苏光辉，田文喜（2021）. 碱金属高温热管启动运行特性分析. 《原子能科学技术》.
507. 桂民洋，田文喜，吴迪，陈荣华，张魁，苏光辉，秋穗正（2021）. 棒束子通道CHF机理模型开发及初步验证. 《原子能科学技术》.
508. 许芝春，张亚培，苏光辉，田文喜，秋穗正（2021）. 堆芯熔融物与混凝土相互作用数值模拟研究. 《核动力工程》.DOI
509. 陈宇彤，张大林，梁禹，周磊，田文喜，秋穗正，苏光辉（2021）. 快堆绕丝组件三维精细化多孔介质模型与验证. 《核动力工程》.DOI
510. 邓阳斌，殷园，巫英伟，田文喜，秋穗正，苏光辉（2021）. 基于蒙特卡罗方法的碳化硅包壳失效概率论评价. 《核科学与工程》.
511. Hongping Sun, Jian Deng, Yuejian Luo, Ming Zhang, Youyou Xu, Xiaoli Wu, Lili Liu, Suizheng Qiu, G.H. Su (2021). Investigation of fission products distribution effected by spray system in PWR containment during severe accidents. Annals of Nuclear Energy.DOI
512. Jiatong Tan, Quan Li, Bo Zhao, Chao Ma, Yingwei Wu, Yuanming Li, Jing Zhang, Yanan He, Tianzhou Ye, Cheng Zhang, Wenxi Tian, Guanghui Su, Suizheng Qiu (2021). Multi-Objective Optimization Design of Plate-type Fuel via Co-simulation Method. Annals of Nuclear Energy.DOI
513. Yin Zhang, Kailun Guo, Chenglong Wang, Simiao Tang, Dalin Zhang, Wenxi Tian, G.H. Su, Suizheng Qiu (2021). Numerical analysis of segmented thermoelectric generators applied in the heat pipe cooled nuclear reactor. Applied Thermal Engineering.DOI
514. Wei Sun, Chao Xu, Yizhen Wang, Suizheng Qiu, Yusheng Liu, Hao Fu (2021). BEPU Analysis in LBLOCA Safety Review Calculation. Sustainability.DOI
515. Simiao Tang, Xiao Liu, Chenglong Wang, Dalin Zhang, G.H. Su, Wenxi Tian, Suizheng Qiu (2021). Thermal-electrical coupling characteristic analysis of the heat pipe cooled reactor with static thermoelectric conversion. Annals of Nuclear Energy.DOI
516. Ji Zhang, Mingjun Wang, Chong Chen, Wenxi Tian, Suizheng Qiu, G.H. Su (2021). CFD investigation of the cold wall effect on CHF in a 5 × 5 rod bundle for PWRs. Nuclear Engineering and Design.DOI
517. Yupeng Yang, Chenglong Wang, Dalin Zhang, Zhike Lan, Dahuan Zhu, Suizheng Qiu, G.H. Su, Wenxi Tian (2021). Numerical analysis of liquid metal helical coil once-through tube steam generator. Annals of Nuclear Energy.DOI
518. Yonglin Li, Wenxi Tian, Ronghua Chen, Tangtao Feng, Suizheng Qiu, G.H. Su (2021). Research on the nuclear fuel rods melting behaviors by alternative material experiments. Journal of Nuclear Materials.DOI
519. Yuchen Huo, Hao Yu, Mingjun Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2021). Development and application of TaSNAM 2.0 for advanced pressurized water reactor. Annals of Nuclear Energy.DOI
520. Chen Wang, Chenglong Wang, Yan Zhang, Dalin Zhang, Wenxi Tian, Guanghui Su, Suizheng Qiu (2021). Flow and heat transfer evaluation of lead-bismuth eutectic coolant for nuclear power application. Nuclear Engineering and Design.DOI
521. Hao Sun, Xiao Liu, Haoyu Liao, Chenglong Wang, Jing Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2021). Experiment study on thermal behavior of a horizontal high-temperature heat pipe under motion conditions. Annals of Nuclear Energy.DOI
522. Zhichun Xu, Yapei Zhang, Zijie Wu, Dekui Zhan, G.H. Su, Wenxi Tian, Suizheng Qiu (2021). Experimental study on molten corium-concrete interaction with simulant metal and oxide. Annals of Nuclear Energy.DOI
523. Zhichun Xu, Yapei Zhang, Kui Zhang, Zijie Wu, Dekui Zhan, G.H. Su, Wenxi Tian, Suizheng Qiu (2021). Experimental and numerical investigation on characteristics of MCCI with exothermic thermite. Nuclear Engineering and Design.DOI
524. Fengrui Xiang, Yanan He, Yuhang Niu, Chaoqun Deng, Yingwei Wu, Kunpeng Wang, Wenxi Tian, G.H. Su, Suizheng Qiu (2021). A new method to simulate dispersion plate-type fuel assembly in a multi-physics coupled way. Annals of Nuclear Energy.DOI
525. Zhao Xin Jin, Chenglong Wang, Xiao Liu, Zhiwen Dai, Wenxi Tian, Guanghui Su, Suizheng Qiu (2021). Operation and safety analysis of space lithium-cooled fast nuclear reactor. Annals of Nuclear Energy.DOI
526. Kai Liu, Mingjun Wang, Fujun Gan, Wenxi Tian, Suizheng Qiu, G.H. Su (2021). Numerical investigation of flow and heat transfer characteristics in plate-type fuel channels of IAEA MTR based on OpenFOAM. Progress in Nuclear Energy.DOI
527. Yupeng Yang, Yong Li, Chenglong Wang, Tao Wang, Zhike Lan, Dalin Zhang, Suizheng Qiu, G.H. Su, Wenxi Tian (2021). Parametric sensitivity analysis of liquid metal helical coil once-through tube steam generator. Nuclear Engineering and Design.DOI
528. Ruiyu Sun, Liangpeng Wu, Wen Jiang Ding, Ronghua Chen, Wenxi Tian, Suizheng Qiu, G.H. Su (2021). From melt jet break-up to debris bed formation: A review of melt evolution model during fuel-coolant interaction. Annals of Nuclear Energy.DOI
529. Xianan Du, Yushan Tao, Youqi Zheng, Chenglong Wang, Yongping Wang, Suizheng Qiu, Bin Zhang, Zian Zhai (2021). Reactor core design of UPR-s: A nuclear reactor for silence thermoelectric system NUSTER. Nuclear Engineering and Design.DOI
530. Zichao Han, Jing Zhang, Mingjun Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2021). A modified system analysis code for thermo-hydraulic calculation of hydrogen in a nuclear thermal propulsion (NTP) system. Annals of Nuclear Energy.DOI
531. Kun Zhang, Tairan Yang, Haifan Liao, Xiangdong Xie, R.H. Chen, Wenxi Tian, G.H. Su, Suizheng Qiu (2021). Development of fuel rod behavior analysis code and its application to supercritical CO2 cooled nuclear reactor. Annals of Nuclear Energy.DOI
532. Kun Zhang, Xiangdong Xie, Tairan Yang, Xinze Li, R.H. Chen, Wenxi Tian, G.H. Su, Suizheng Qiu (2021). Program development and study on supercritical CO2-cooled reactor sub-channel thermal hydraulic. Annals of Nuclear Energy.DOI
533. Chenglong Wang, Panxiao Li, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su, Jian Deng (2021). Experimental study on the influence of heating surface inclination angle on heat transfer and CHF performance for pool boiling. Nuclear Engineering and Technology.DOI
534. Xiaohan Zhao, Yixiang Liao, Mingjun Wang, Kui Zhang, G.H. Su, Wenxi Tian, Suizheng Qiu, Dirk Lucas (2021). Numerical simulation of micro-crack leakage on steam generator heat transfer tube. Nuclear Engineering and Design.DOI
535. Yichao Ma, Jing Zhang, Mingjun Wang, Wenxi Tian, Ronghua Chen, Yingwei Wu, G.H. Su, Suizheng Qiu (2021). Performance analysis of PRHRS in primary and secondary circuit for offshore floating nuclear plant. Annals of Nuclear Energy.DOI
536. Shihao Wu, Yapei Zhang, Dong Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2021). Assessment of the severe accident code MIDAC based on FROMA, QUENCH-06&16 experiments. Nuclear Engineering and Technology.DOI
537. Shibao Wang, Konstantin Mikityuk, Đorđe Petrović, Dalin Zhang, G.H. Su, Suizheng Qiu, Wenxi Tian (2021). Validation of TRACE capability to simulate unprotected transients in Sodium Fast Reactor using FFTF LOFWST Test #13. Annals of Nuclear Energy.DOI
538. Ping Song, Tangtao Feng, Dalin Zhang, Lie Chen, Shaodan Li, Yuansheng Lin, Suizheng Qiu (2021). Numerical Analysis on the Thermal-Hydraulic Characteristics for the Reactor Main Vessel Cooling System of Chinese Sodium Cooled Fast Reactor.DOI
539. Linrong Ye, Hao Yu, Mingjun Wang, Qianglong Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2021). CFD/RELAP5 coupling analysis of the ISP No. 43 boron dilution experiment. Nuclear Engineering and Technology.DOI
540. Jinshun Wang, Qinghang Cai, Ronghua Chen, Xinkun Xiao, Yonglin Li, Wenxi Tian, Suizheng Qiu, G.H. Su (2021). Numerical analysis of melt migration and solidification behavior in LBR severe accident with MPS method. Nuclear Engineering and Technology.DOI
541. Chenglong Wang, Ran Zhang, Kailun Guo, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2021). Dynamic simulation of a space gas-cooled reactor power system with a closed Brayton cycle. Frontiers in Energy.DOI
542. Zhipeng Liu, Daishun Huang, Chenglong Wang, Qifan Yu, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2021). Flow and heat transfer analysis of lead–bismuth eutectic flowing in a tube under rolling conditions. Nuclear Engineering and Design.DOI
543. Liangguo Li, B. Long, Jianming Yu, Qianhua Su, Donghua Lu, Yingwei Wu, Suizheng Qiu, Guanghui Su, Wenxi Tian, Xiaohang Wu, Jiyong Liu, Peng Ju (2021). Research on scaling analysis and design parameters of integral test facilities for PWR. Annals of Nuclear Energy.DOI
544. Yangyang Wang, Yanhua Guo, Yingwei Wu, Yu Liu, Luguo Liu, Cheng Zhang, Ze Zhang, Jing Zhang, Suizheng Qiu, G.H. Su, Wenxi Tian (2021). Preliminary analysis on the thermal-mechanical behavior of dispersed plate-type fuel under reactivity insertion accident. Annals of Nuclear Energy.DOI
545. Huijian Huang, Chong Chen, Luguo Liu, Yu Liu, Linfeng Li, Hao Yu, Mingjun Wang, Suizheng Qiu (2021). Study on Flow Boiling Characteristics in Rectangle Channel After Formation of Blisters. Frontiers in Energy Research.DOI
546. Cheng Zhang, Yingwei Wu, Yanan He, Yuanming Li, Shichao Liu, Jing Zhang, Wenxi Tian, G.H. Su, Suizheng Qiu, Junmei Wu (2021). Investigation on thermo-mechanical performance of fully ceramic microencapsulated fuel. Journal of Nuclear Materials.DOI
547. Hao Qin, Chenglong Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2021). Energy allocation optimization of the gas-cooled space nuclear reactor. Applied Thermal Engineering.DOI
548. Yuliang Fang, Hao Qin, Chenglong Wang, Lei Zhou, Jing Zhang, Dalin Zhang, Wenxi Tian, G.H. Su, Suizheng Qiu (2021). Numerical investigation on thermohydraulic performance of high temperature hydrogen in twisted rod channels. Annals of Nuclear Energy.DOI
549. Zhiwen Dai, Chenglong Wang, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2021). Impact of axial power distribution on thermal-hydraulic characteristics for thermionic reactor. Nuclear Engineering and Technology.DOI
550. Haoran Ju, Hao Yu, Mingjun Wang, Minfu Zhao, Wenxi Tian, Tiancai Liu, G.H. Su, Suizheng Qiu (2021). LES and URANS study on turbulent flow through 3 × 3 rod bundle with spacer grid and mixing vanes using spectral element method. Annals of Nuclear Energy.DOI
551. Wenwen Zhang, Kaichao Sun, Chenglong Wang, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2021). Preliminary design and assessment of a heat pipe residual heat removal system for the reactor driven subcritical facility. Nuclear Engineering and Technology.DOI
552. Yutong Chen, Dalin Zhang, Yu Liang, Shibao Wang, Qifan Yu, Chenglong Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2021). Preliminary development and validation of ACENA code for heavy liquid metal-gas two phase flow simulation. Annals of Nuclear Energy.DOI
553. X.A. Wang, Dalin Zhang, Mingjun Wang, Yandong Hou, Wenxi Tian, Suizheng Qiu, G.H. Su (2021). Numerical investigation for the heat transfer mechanisms between subchannels of bar rod bundles cooled by liquid sodium. Annals of Nuclear Energy.DOI
554. Yukun Zhou, Jun Wang, Zehua Guo, Yanan He, Yapei Zhang, Suizheng Qiu, G.H. Su, Michael L. Corradini (2021). 3D-2D coupling multi-dimension simulation for the heat pipe micro-reactor by MOOSE&SAM. Progress in Nuclear Energy.DOI
555. Irfan Khan, Mingjun Wang, Yapei Zhang, Wenxi Tian, G.H. Su, Suizheng Qiu (2021). CFD study on onset of liquid entrainment through ADS-4 branch line in AP1000. Nuclear Engineering and Design.DOI
556. Chenglong Wang, Di Wu, Minyang Gui, Rong Cai, Dahuan Zhu, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2021). Flow blockage analysis for fuel assembly in a lead-based fast reactor. Nuclear Engineering and Technology.DOI
557. Zhixing Tian, Chenglong Wang, Jinlu Huang, Kailun Guo, Dalin Zhang, Xiao Liu, G.H. Su, Wenxi Tian, Suizheng Qiu (2021). Code development and analysis on the operation of liquid metal high temperature heat pipes under full condition. Annals of Nuclear Energy.DOI
558. Haoyu Liao, Kailin Lu, Chenxi Li, Hao Yao, Yanan He, Yingwei Wu, G.H. Su, Suizheng Qiu (2021). Development of a transient module based on FROBA-ROD code and assessment for fuel rod performance under reactivity-initiated accident. Annals of Nuclear Energy.DOI
559. Yuhang Niu, Yanan He, Fengrui Xiang, Jing Zhang, Yingwei Wu, Wenxi Tian, G.H. Su, Suizheng Qiu (2021). Automatic differentiation approach for solving one-dimensional flow and heat transfer problems. Annals of Nuclear Energy.DOI
560. Bing Tan, Xi Wang, Yingwei Wu, Wenxi Tian, Suizheng Qiu, G.H. Su (2021). Vapor condensation with low air mass fraction inside water seal branch tube under free convection. Nuclear Engineering and Design.DOI
561. Wenxi Tian, Minyang Gui, Di Wu, Ronghua Chen, G.H. Su, Suizheng Qiu (2021). Study on flow instability in natural circulation loop with parallel channels under moving condition. Nuclear Engineering and Design.DOI
562. Yingjie Wang, Mingjun Wang, Jing Zhang, Suizheng Qiu, Wenxi Tian, G.H. Su (2021). Large eddy simulation on the mixing characteristics of liquid sodium at the core outlet of sodium cooled fast reactors (SFR). Annals of Nuclear Energy.DOI
563. Yonglin Li, Wenxi Tian, Ronghua Chen, Guangtao Duan, Suizheng Qiu, G.H. Su (2021). Numerical investigation of oxidation and dissolution behavior in the fuel cladding using MPS-CV method. Nuclear Engineering and Design.DOI
564. Cheng Zhang, Yangyang Wang, Yingwei Wu, Shichao Liu, Ping Chen, Yanan He, Chunyu Yin, Jing Zhang, Wenxi Tian, G.H. Su, Suizheng Qiu, Junmei Wu (2021). Preliminary numerical investigation of TRISO-matrix interface debonding characteristics in fully ceramic microencapsulated fuel. Annals of Nuclear Energy.DOI
565. Irfan Khan, Mingjun Wang, Muhammad Abdul Basit, Wenxi Tian, G.H. Su, Suizheng Qiu (2021). CFD modeling of liquid entrainment through vertical T-junction of fourth stage automatic depressurization system (ADS-4). Annals of Nuclear Energy.DOI
566. Linyi Yang, Chenglong Wang, Hao Qin, Dalin Zhang, Wenxi Tian, G.H. Su, Suizheng Qiu (2021). Operation performance analysis of a liquid metal droplet radiator for space nuclear reactor. Annals of Nuclear Energy.DOI
567. Zeqin Zhang, Xiaoming Chai, Chenglong Wang, Hao Sun, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2021). Numerical investigation on startup characteristics of high temperature heat pipe for nuclear reactor. Nuclear Engineering and Design.DOI
568. Zhixing Tian, Xiao Liu, Chenglong Wang, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2021). Experimental investigation on the heat transfer performance of high-temperature potassium heat pipe for nuclear reactor. Nuclear Engineering and Design.DOI
569. Lei Zhou, Dalin Zhang, Shibao Wang, Yapeng Liu, Chenglong Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2021). Phenomena identification and ranking table of station blackout accidents for China sodium cooled fast reactor. Annals of Nuclear Energy.DOI
570. Youchun Chen, Dalin Zhang, Rongshuan Xu, Xin Min, Shibao Wang, Bo Wang, Chenglong Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2021). Start-up characteristics for the test facility of a prototype sodium heated OTSG. Nuclear Engineering and Design.DOI
571. Bing Tan, Wenxi Tian, R. H. Chen, Suizheng Qiu, G.H. Su (2021). Experimental Study of Air-Steam–Mixture Condensation Underneath Containment Vessel Surface. Nuclear Science and Engineering.DOI
572. Mingjun Wang, Lianfa Wang, Yingjie Wang, Wenxi Tian, Jian Deng, G.H. Su, Suizheng Qiu (2021). CFD Simulation of thermal hydraulic characteristics in a typical upper plenum of RPV. Frontiers in Energy.DOI
573. Tianzhou Ye, Huan Yao, Yingwei Wu, Jing Lin Zhang, Junmei Wu, Mingjun Wang, Wenxi Tian, G.H. Su, Suizheng Qiu (2021). Primary radiation damage characteristics in displacement cascades of FeCrAl alloys. Journal of Nuclear Materials.DOI
574. Hao Yao, Yujian Huang, Yingwei Wu, Jing Zhang, G.H. Su, Wenxi Tian, Suizheng Qiu (2021). Numerical analysis of liquid fall type gas entrainment in pool-type fast reactor. Annals of Nuclear Energy.DOI
575. Chenglong Wang, Yan Zhang, Dalin Zhang, Zhike Lan, Wenxi Tian, G.H. Su, Suizheng Qiu (2021). Numerical study of oxygen transport characteristics in lead-bismuth eutectic for gas-phase oxygen control. Nuclear Engineering and Technology.DOI
576. Simiao Tang, Chenglong Wang, Dalin Zhang, Wenxi Tian, G.H. Su, Suizheng Qiu (2021). Thermoelectric performance study on a heat pipe thermoelectric generator for micro nuclear reactor application. International Journal of Energy Research.DOI
577. Yongquan Li, Ping Song, Tangtao Feng, Mingjun Wang, Dalin Zhang, Wenxi Tian, Suizheng Qiu (2021). Numerical study on improved design of passive residual heat removal system for China pressurizer reactor. Nuclear Engineering and Design.DOI
578. Zhiwen Dai, Chenglong Wang, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2021). Design and heat transfer optimization of a 1 kW free-piston stirling engine for space reactor power system. Nuclear Engineering and Technology.DOI
579. Shibao Wang, Dalin Zhang, Liang Yu, Xin’an Wang, Suizheng Qiu, G.H. Su, Wenxi Tian (2021). Development a methodology for evaluating inter‐assembly heat transfer effect through reactor core in system safety analysis of sodium‐cooled fast reactor. International Journal of Energy Research.DOI
580. Zhipeng Liu, Chenglong Wang, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2021). Thermal-hydraulic analysis of a lead–bismuth small modular reactor under moving conditions. Annals of Nuclear Energy.DOI
581. X. A. Wang, Dalin Zhang, Mingjun Wang, Yapeng Liu, Lei Zhou, Shibao Wang, Liang Yu, Wenxi Tian, Suizheng Qiu, G.H. Su (2021). Generating Hexahedral Mesh for Wire-wrapped Fuel Assembly With RBF Mesh Deformation Method. Frontiers in Energy Research.DOI
582. Yan Zhang, Dalin Zhang, Chenglong Wang, Zhike Lan, Wenxi Tian, G.H. Su, Suizheng Qiu (2021). Oxygen transport analysis in lead-bismuth eutectic coolant for solid-phase oxygen control. Annals of Nuclear Energy.DOI
583. Zhen-Hui Liang, Suizheng Qiu (2021). Experimental analysis on thermal characteristics of two-phase water in narrow rectangular channels. Nuclear Engineering and Design.DOI
584. Hao Yao, Guo Chen, Kailin Lu, Yingwei Wu, Wenxi Tian, G.H. Su, Suizheng Qiu (2021). Study on the systematic thermal-hydraulic characteristics of helical coil once-through steam generator. Annals of Nuclear Energy.DOI
585. Shiying Wei, Weimin Ma, Chenglong Wang, Ronghua Chen, Wenxi Tian, Suizheng Qiu, G.H. Su (2021). Development and validation of transient thermal‐hydraulic evaluation code for a lead‐based fast reactor. International Journal of Energy Research.DOI
586. Hao Yao, Guo Chen, Kailin Lu, Haoyu Liao, Yingwei Wu, Wenxi Tian, G.H. Su, Suizheng Qiu (2021). Study on the thermal and geometrical parameters of helical coil once-through steam generator system. International Journal of Advanced Nuclear Reactor Design and Technology.DOI
587. Qiang Lian, Wenxi Tian, Suizheng Qiu, G.H. Su (2021). Development of a three-dimensional method for thermal-hydraulics/neutronics coupling analysis and its application on CFETR helium-cooled solid breeder blanket. International Journal of Advanced Nuclear Reactor Design and Technology.DOI
588. Hao Qin, Chenglong Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2021). Experimental investigation on heat transfer characteristics of high temperature air in round tube. International Journal of Advanced Nuclear Reactor Design and Technology.DOI
589. Chenxi Li, Haoyu Liao, Yingwei Wu, Wenxi Tian, G.H. Su, Suizheng Qiu (2021). Thermal-hydraulic performance evaluation of annular fuel based on modified FROBA-ANNULAR. International Journal of Advanced Nuclear Reactor Design and Technology.DOI
590. Haoyu Liao, Chenxi Li, Yanan He, Yingwei Wu, Yapei Zhang, Wenxi Tian, G.H. Su, Suizheng Qiu (2021). Analysis for fuel rod performance under LOCA based on the FROBA-ROD 2.0 code. International Journal of Advanced Nuclear Reactor Design and Technology.DOI
591. Yu Liang, Mingjun Wang, Zhen Li, Haoyu Liao, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2021). Low temperature overpressurization analysis for CPR1000. International Journal of Advanced Nuclear Reactor Design and Technology.DOI
592. Ran Zhang, Carlo Fiorina, Stefan Radman, Suizheng Qiu (2021). Preliminary Thermal-Hydraulics Analysis of SFR Assembly Windows Under Sodium Boiling Transients. Transactions of the American Nuclear Society.DOI
593. 朱磊，康小亚，江新标，李华琪，杨宁，秋穗正（2020）. 汽阳极多管AMTEC辐射与导热模型的研究. 《能源工程》.DOI
594. 侯延栋，汪刘，张魁，王明军，巫英伟，田文喜，苏光辉，秋穗正（2020）. 六边形排列的7棒束通道内液态钠流动换热特性试验研究. 《原子能科学技术》.
595. 朱磊，江新标，康小亚，田晓艳，李华琪，秋穗正（2020）. 汽阳极多管AMTEC性能分析方法及参数优化分析. 《工程热物理学报》.
596. 孙汝雷，张大林，周健成，宋功乐，田文喜，苏光辉，秋穗正（2020）. 窄矩形通道两相流动沸腾压降特性实验研究. 《原子能科学技术》.
597. 房玉良，秦浩，王成龙，苏光辉，田文喜，秋穗正（2020）. 高温、高流速氢气在圆管内流动换热特性研究. 《原子能科学技术》.
598. 刘明皓，张玉龙，王成龙，张大林，秋穗正，李毅，尹莎莎，刘航，杨红发（2020）. 熔盐堆热管式非能动余热排出系统建模及程序开发. 《原子能科学技术》.
599. 蔚江涛，田文喜，苏光辉，秋穗正（2020）. AP1000稳压器波动管竖直管段空气-水CCFL实验研究. 《核动力工程》.DOI
600. 陈冲，王明军，田文喜，章静，秋穗正，苏光辉（2020）. 核电厂“死管段”现象CFD研究. 《核动力工程》.
601. 刘逍，田智星，王成龙，苏光辉，田文喜，秋穗正（2020）. 高温热管传热特性实验研究. 《核动力工程》.DOI
602. 朱磊，江新标，李华琪，陈森，田晓艳，秋穗正（2020）. 圆锥角对汽阳极AMTEC圆锥形蒸发器性能影响分析. 《核动力工程》.DOI
603. 田智星，刘逍，王成龙，苏光辉，田文喜，秋穗正（2020）. 高温钾热管稳态运行传热特性研究. 《原子能科学技术》.
604. Shaopeng He, Mingjun Wang, Jing Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2020). Numerical simulation of three-dimensional flow and heat transfer characteristics of liquid lead–bismuth. Nuclear Engineering and Technology.DOI
605. Zhiwen Dai, Chenglong Wang, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2020). Numerical simulation on thermal‐hydraulic and thermoelectric characteristics of the TOPAZ‐II reactor core. International Journal of Energy Research.DOI
606. Qifan Yu, Yan Zhang, Chenglong Wang, Chao Guo, Jian Deng, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2020). Numerical simulation of bubble transport during steam generator tube rupture accident of Lead-cooled Fast Reactor. Annals of Nuclear Energy.DOI
607. Jun Li, Mingjun Wang, Di Fang, Jie Wang, Dong Liu, Wenxi Tian, Suizheng Qiu, G.H. Su (2020). CFD simulation on the transient process of coolant mixing phenomenon in reactor pressure vessel. Annals of Nuclear Energy.DOI
608. Muhammad Abdul Basit, Wenxi Tian, Ronghua Chen, Romana Basit, Suizheng Qiu, G.H. Su (2020). Investigation of single bubble behavior under rolling motions using multiphase MPS method on GPU. Nuclear Engineering and Technology.DOI
609. Kun Zhang, Zhengfei Zhu, Binghan Shang, Gongle Song, Wenxi Tian, Jian Deng, G.H. Su, Suizheng Qiu (2020). Experimental investigation on flow regimes and transitions of steam-water two-phase flow in narrow rectangular horizontal channels. Progress in Nuclear Energy.DOI
610. Jun Li, Di Fang, Chao Guo, Mingjun Wang, Jian Deng, Wenxi Tian, Suizheng Qiu, G.H. Su (2020). Numerical Study on the Thermal Hydraulic Characteristics in a Wire-Wrapped Assembly of LFRs. Frontiers in Energy Research.DOI
611. Kailun Guo, Chenglong Wang, Dalin Zhang, Wenxi Tian, G.H. Su, Suizheng Qiu (2020). Investigations of near-wall bubble behavior in wire heaters pool boiling. Thermal Science.DOI
612. J. Zhang, S.S. Yin, Liang Chen, Yaoxiang Ma, M.J. Wang, Heng Fu, Yingwei Wu, Wenxi Tian, Suizheng Qiu, G.H. Su (2020). A study on the dynamic characteristics of the secondary loop in nuclear power plant. Nuclear Engineering and Technology.DOI
613. Yapeng Liu, Dalin Zhang, Ping Song, Shibao Wang, Liang Yu, Lei Zhou, Chenglong Wang, Mingjun Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2020). Analysis of the natural circulation test of PHENIX reactor by the THACS code. Annals of Nuclear Energy.DOI
614. Hao Sun, Simiao Tang, Chenglong Wang, Jing Zhang, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2020). Numerical simulation of a small high-temperature heat pipe cooled reactor with CFD methodology. Nuclear Engineering and Design.DOI
615. Hang Xia, Yingwei Wu, Wenxi Tian, G.H. Su, Suizheng Qiu (2020). Development of thermal hydraulic analysis code of annular fuel under flow blockage condition. Annals of Nuclear Energy.DOI
616. Chong Chen, Xingjun Wang, Mingjun Wang, Yubo Qi, Jing Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2020). CFD simulation of thermal hydraulic phenomena in enclosed cavity of nuclear power plants. Annals of Nuclear Energy.DOI
617. Shibao Wang, Dalin Zhang, Yapeng Liu, Chenglong Wang, Suizheng Qiu, G.H. Su, Wenxi Tian (2020). An experiment‐based validation of a system code for prediction of passive natural circulation in sodium‐cooled fast reactor. International Journal of Energy Research.DOI
618. Chenglong Wang, Xiao Liu, Minghao Liu, Simiao Tang, Zhixing Tian, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2020). Experimental study on heat transfer limit of high temperature potassium heat pipe for advanced reactors. Annals of Nuclear Energy.DOI
619. Yutong Chen, Liang Yu, Dalin Zhang, Shibao Wang, Chenglong Wang, Jian Deng, Wenxi Tian, Suizheng Qiu, G.H. Su (2020). A porous medium model for simulating conjugate heat transfer between wire-wrapped fuel bundles under forced and mixed convection. Annals of Nuclear Energy.DOI
620. Di Wu, Chenglong Wang, Minyang Gui, Zhike Lan, Qi Lu, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2020). Improvement and validation of a sub‐channel analysis code for a lead‐cooled reactor with wire spacers. International Journal of Energy Research.DOI
621. Liang Yu, Yutong Chen, Dalin Zhang, Xiao Liu, Jian Deng, Chenglong Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2020). Experimental and numerical investigation on flow characteristics of inter-wrapper channel in LMFBR. Annals of Nuclear Energy.DOI
622. Lei Zhu, Lixin Chen, Huaqi Li, Da Li, Ning Yang, Xinbiao Jiang, Suizheng Qiu (2020). Performance analysis of alkali metal thermoelectric converter and segmented thermoelectric generator hybrid system based on a comprehensive model. Applied Thermal Engineering.DOI
623. Xiaohan Zhao, Mingjun Wang, Ge Ping Wu, Jing Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2020). The development of high fidelity Steam Generator three dimensional thermal hydraulic coupling code: STAF-CT. Nuclear Engineering and Technology.DOI
624. Jun Zhang, Chenglong Wang, Jing Zhang, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2020). Design research for the porous hexagonal prism shaped fuel element adopted in nuclear thermal propulsion reactor based on neutronics and thermal-hydraulics coupled method. Annals of Nuclear Energy.DOI
625. Jinrong Qiu, Longze Li, Yun Tai, Shiwei Yao, G.H. Su, Suizheng Qiu (2020). MELCOR simulation of the SBLOCA induced severe accident for the SMR in a floating nuclear power plant. Progress in Nuclear Energy.DOI
626. Dalin Zhang, Rongshuan Xu, Youchun Chen, Bo Wang, Chenglong Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2020). Preliminary study of parameter uncertainty influence on thermal design and analysis for sodium heated once-through steam generator. Nuclear Engineering and Design.DOI
627. Kailun Guo, Ronghua Chen, Chenglong Wang, Suizheng Qiu, Wenxi Tian, G.H. Su (2020). Modeling of early stage droplet spreading based on numerical simulations. Nuclear Engineering and Design.DOI
628. Rongshuan Xu, Ping Song, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2020). Numerical analysis on flow instability of parallel channels in steam generator for sodium‐cooled fast reactor. International Journal of Energy Research.DOI
629. Hao Qin, Chenglong Wang, Dalin Zhang, Wenxi Tian, G.H. Su, Suizheng Qiu (2020). Parametric investigation of radiation heat transfer and evaporation characteristics of a liquid droplet radiator. Aerospace Science and Technology.DOI
630. Mingjun Wang, Yingjie Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2020). Recent progress of CFD applications in PWR thermal hydraulics study and future directions. Annals of Nuclear Energy.DOI
631. Shibao Wang, Dalin Zhang, Suizheng Qiu, G.H. Su, Wenxi Tian (2020). A practical methodology devoted to pool‐type phenomena simulation in safety analysis for sodium‐cooled fast reactor. International Journal of Energy Research.DOI
632. Chenglong Wang, Yupeng Yang, Minghao Liu, Dalin Zhang, Suizheng Qiu, G.H. Su, Wenxi Tian, Jian Deng (2020). Transient thermal‐hydraulic analysis of heat pipe cooled passive residual heat removal system of molten salt reactor. International Journal of Energy Research.DOI
633. Linrong Ye, Mingjun Wang, Xinan Wang, Jian Deng, Yan Xiang, Wenxi Tian, Suizheng Qiu, G.H. Su (2020). Thermal Hydraulic and Neutronics Coupling Analysis for Plate Type Fuel in Nuclear Reactor Core. Science and Technology of Nuclear Installations.DOI
634. Ran Zhang, Kailun Guo, Chenglong Wang, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su, Jian Deng (2020). Thermal‐hydraulic analysis of gas‐cooled space nuclear reactor power system with closed Brayton cycle. International Journal of Energy Research.DOI
635. Simin Luo, P. Chen, Jingyuan Bai, Y.K. Li, Y.P. Zhang, Suizheng Qiu, G.H. Su, Wenxi Tian, Dekui Zhan (2020). Experimental research on the influence of rolling motions on the convection behaviors inside two-layer corium pools. Progress in Nuclear Energy.DOI
636. Qiang Lian, Wenxi Tian, Suizheng Qiu, G.H. Su (2020). Neutronics influence of poloidal nonuniform neutron wall loading on helium-cooled ceramic breeder blanket for CFETR. Fusion Engineering and Design.DOI
637. Zhichun Xu, Yapei Zhang, G.H. Su, Wenxi Tian, Suizheng Qiu (2020). Numerical Simulation of Concrete Ablation and Corium Cooling for Molten Corium-Concrete Interaction (MCCI).DOI
638. Simin Luo, Hongping Sun, Yapei Zhang, Junmei Wu, Suizheng Qiu, G.H. Su (2020). Research on Natural Convection of Two-Layer Corium Pools.DOI
639. Hao Qin, Yuliang Fang, Chenglong Wang, Wenxi Tian, Suizheng Qiu, G.H. Su, Jian Deng (2020). Numerical investigation on heat transfer characteristics of helium‐xenon gas mixture. International Journal of Energy Research.DOI
640. Yan Zhang, Chenglong Wang, Rong Cai, Zhike Lan, Yaou Shen, Dalin Zhang, Wenxi Tian, G.H. Su, Suizheng Qiu (2020). Experimental investigation on flow and heat transfer characteristics of lead–bismuth eutectic in circular tubes. Applied Thermal Engineering.DOI
641. Minyang Gui, Wenxi Tian, Di Wu, Ronghua Chen, G.H. Su, Suizheng Qiu (2020). Program development and preliminary CHF characteristics analysis for natural circulation loop under moving condition. Nuclear Engineering and Technology.DOI
642. Zhiwen Dai, Chenglong Wang, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2020). Design and analysis of a free-piston stirling engine for space nuclear power reactor. Nuclear Engineering and Technology.DOI
643. Hao Yu, Haoran Ju, Mingjun Wang, Jing Zhang, Suizheng Qiu, Wenxi Tian, G.H. Su (2020). Study of boron diffusion models and dilution accidents in nuclear reactor: A comprehensive review. Annals of Nuclear Energy.DOI
644. Hongping Sun, Jian Deng, Yapei Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2020). Numerical method development for oxidation particle formation during sodium spray fires in SFR containment. Annals of Nuclear Energy.DOI
645. Gongle Song, Di Wu, Rulei Sun, Yu Liang, Dalin Zhang, Jian Deng, G.H. Su, Wenxi Tian, Suizheng Qiu (2020). Theoretical study of steady-state characteristics of natural circulation system. Annals of Nuclear Energy.DOI
646. Yun Wang, Kuanghan Deng, Junmei Wu, G.H. Su, Suizheng Qiu (2020). A mechanism of heat transfer enhancement or deterioration of nanofluid flow boiling. International Journal of Heat and Mass Transfer.DOI
647. Haoyu Liao, Yangyang Wang, Yuanming Li, Kunpeng Wang, Yangbin Deng, Min Su, Yingwei Wu, Mingjun Wang, Suizheng Qiu (2020). 3D fluid-solid coupling simulation for plate-type nuclear fuel assemblies under the irradiation condition. Progress in Nuclear Energy.DOI
648. Chenglong Wang, Hao Qin, Dalin Zhang, Wenxi Tian, G.H. Su, Suizheng Qiu (2020). Numerical investigation of natural convection characteristics of a heat pipe-cooled passive residual heat removal system for molten salt reactors. Nuclear Science and Techniques.DOI
649. Rui Zhang, Tenglong Cong, G.H. Su, Jianjun Wang, Suizheng Qiu (2020). Investigation on the critical heat flux in typical 5 by 5 rod bundle at conditions prototypical of PWR based on CFD methodology. Applied Thermal Engineering.DOI
650. Jiancheng Zhou, Tianzhou Ye, Dalin Zhang, Gongle Song, Rulei Sun, Jian Deng, Wenxi Tian, G.H. Su, Suizheng Qiu (2020). Experimental study on vertically upward steam-water two-phase flow patterns in narrow rectangular channel. Nuclear Engineering and Technology.DOI
651. Mingjun Wang, Lianfa Wang, Xingjun Wang, Jian Ge, Wenxi Tian, Suizheng Qiu, G.H. Su (2020). CFD simulation on the flow characteristics in the PWR lower plenum with different internal structures. Nuclear Engineering and Design.DOI
652. Chenxi Li, Yingwei Wu, Yangyang Wang, Kunpeng Wang, Mingjun Wang, Wenxi Tian, G.H. Su, Suizheng Qiu (2020). Analysis on the behavior of dispersed plate-type fuel based on fluid-solid coupling method. Progress in Nuclear Energy.DOI
653. Cheng Zhang, Yingwei Wu, Shichao Liu, Chen Ping, Wei Li, Chaoqun Deng, Jing Zhang, G.H. Su, Suizheng Qiu, Junmei Wu (2020). Multidimensional multiphysics modeling of TRISO particle fuel with SiC/ZrC coating using modified fission gas release model. Annals of Nuclear Energy.DOI
654. Zhichun Xu, Yapei Zhang, Bo Lin, Simin Luo, Yukun Zhou, G.H. Su, Wenxi Tian, Suizheng Qiu (2020). Development and application of MOQUICO code to study molten corium-concrete interaction. Annals of Nuclear Energy.DOI
655. Wenwen Zhang, Dalin Zhang, Chenglong Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2020). Conceptual design and analysis of a megawatt power level heat pipe cooled space reactor power system. Annals of Nuclear Energy.DOI
656. 牛钰航，邓超群，巫英伟，苏光辉，秋穗正，刘东，卢忝余，于洋（2019）. 基于JFNK方法的中子——热工全耦合计算分析. 《第十六届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室2019年学术年会论文集》.DOI
657. 秋穗正（2019）. 熔盐堆. 《西安交通大学出版社》.
658. 蔡庆航，陈荣华，李勇霖，章静，田文喜，秋穗正，苏光辉（2019）. 基于MPS方法的HECLA三维瞬态MCCI实验模拟研究. 《第十六届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室2019年学术年会论文集》.DOI
659. 秦浩，王成龙，田文喜，秋穗正，苏光辉（2019）. 兆瓦级气冷空间堆堆芯安全特性研究. 《第十六届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室2019年学术年会论文集》.DOI
660. 连强，田文喜，秋穗正，苏光辉（2019）. 螺旋管及直管内流动不稳定性程序开发及应用研究. 《第十六届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室2019年学术年会论文集》.DOI
661. 李晨曦，廖浩宇，巫英伟，王阳阳，苏光辉，秋穗正，田文喜（2019）. 辐照条件下的板状燃料元件热工机械性能分析. 《第十六届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室2019年学术年会论文集》.DOI
662. 唐思邈，田智星，王成龙，苏光辉，田文喜，秋穗正（2019）. 小型核电源原理样机传热及热电性能研究. 《第十六届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室2019年学术年会论文集》.DOI
663. 王莹杰，王明军，张大林，田文喜，秋穗正，苏光辉（2019）. 基于流固耦合方法的核反应堆板型燃料元件流弹性失稳现象研究. 《第十六届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室2019年学术年会论文集》.DOI
664. 李林峰，王明军，刘卢果，张大林，田文喜，秋穗正，苏光辉（2019）. 考虑气泡滑移效应的壁面沸腾模型开发及其在窄矩形通道内的应用. 《第十六届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室2019年学术年会论文集》.DOI
665. 刘逍，王成龙，苏光辉，秋穗正，田文喜（2019）. 多用途小型核反应堆电源热工水力设计分析. 《第十六届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室2019年学术年会论文集》.DOI
666. 陆恺霖，李晨曦，雷华桢，刘天才，巫英伟，苏光辉，秋穗正（2019）. 燃料质量迁移对单节热离子燃料元件热电转换性能的影响. 《第十六届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室2019年学术年会论文集》.DOI
667. 廖浩宇，陆恺霖，刘卢果，刘余，巫英伟，秋穗正，苏光辉（2019）. 基于FROBA-ROD程序的AP1000燃料棒性能分析与行为预测. 《第十六届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室2019年学术年会》.DOI
668. 李俊，房迪，王明军，田文喜，苏光辉，秋穗正（2019）. 基于标准题UPTF下的压力容器承压热冲击CFD数值模拟. 《第十六届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室2019年学术年会》.DOI
669. 余浩，王明军，秋穗正（2019）. 反应堆内硼稀释事故研究综述. 《第十六届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室2019年学术年会论文集》.DOI
670. 王阳阳，巫英伟，章静，郑美银，苏光辉，秋穗正（2019）. 基于流固耦合的板型燃料组件堵流事故分析. 《第十六届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室2019年学术年会论文集》.DOI
671. 张冉，郭凯伦，王成龙，张大林，秋穗正，苏光辉（2019）. 高温气冷堆空间核电源系统瞬态特性分析. 《第十六届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室2019年学术年会论文集》.DOI
672. 秦浩，王明军，李林峰，田文喜，苏光辉，秋穗正（2019）. 基于OpenFOAM的过冷流动沸腾数值模拟. 《原子能科学技术》.
673. 马在勇，秋穗正，步珊珊，张卢腾，孙皖，潘良明（2019）. 惰性气体对液态金属起始沸腾过热度的影响. 《原子能科学技术》.
674. 李勇霖，陈荣华，蔡庆航，田文喜，左娟莉，朱大欢，邓坚，秋穗正，苏光辉（2019）. 燃料棒熔化行为的粒子网格混合法模拟研究（英文）. 《核动力工程》.
675. 尹莎莎，罗涵禹，秋穗正，黄伟，陈志辉，田野，方华伟（2019）. 模块式小型核反应堆稳压器波动管破口事故分析研究. 《核动力工程》.
676. 伍振兴，李垣明，巫英伟，郑美银，袁攀，秋穗正，苏光辉（2019）. 辐照变形条件下板型燃料组件内热工水力特性研究. 《核动力工程》.DOI
677. 张明昊，陈荣华，郭凯伦，赵大卫，田文喜，苏光辉，秋穗正（2019）. 基于粒子法的流量脉动条件下单气泡上升行为研究. 《核动力工程》.DOI
678. 唐思邈，王成龙，苏光辉，田文喜，秋穗正（2019）. 小型核电源传热及热电特性实验研究. 《核动力工程》.DOI
679. 赵鑫，李亚，仇子铖，秋穗正，苏光辉（2019）. 环形通道内液态金属钠流动传热特性数值模拟. 《核动力工程》.DOI
680. 张冉，王成龙，秋穗正，田文喜，苏光辉（2019）. 空间核电推进球床反应堆热工水力特性数值分析. 《原子能科学技术》.
681. 连强，田文喜，秋穗正，苏光辉（2019）. 基于RELAP5的螺旋管蒸汽发生器热工水力程序研发与验证. 《原子能科学技术》.
682. 代智文，刘天才，王成龙，张大林，田文喜，秋穗正，苏光辉（2019）. 空间核反应堆电源热工水力特性研究综述. 《原子能科学技术》.
683. 秋穗正，张大林，宋苹，王式保，梁禹，王心安，周磊，刘雅鹏（2019）. 钠冷快堆瞬态热工水力及安全分析程序开发. 《原子能科学技术》.
684. 田文喜，王明军，秋穗正，苏光辉（2019）. 基于CFD方法的核动力系统热工安全特性研究进展. 《原子能科学技术》.
685. 郭凯伦，王成龙，秋穗正，苏光辉，田文喜（2019）. 兆瓦级核电推进系统布雷顿循环热电转换特性分析. 《原子能科学技术》.
686. 马在勇，秋穗正，步珊珊，张卢腾，孙皖，潘良明（2019）. 氧化层对液态金属起始沸腾过热度的影响模型. 《原子能科学技术》.
687. 李勇霖，陈荣华，田文喜，秋穗正，苏光辉（2019）. 对流传热问题的粒子-网格混合方法数值模拟. 《原子能科学技术》.
688. 魏诗颖，王成龙，田文喜，秋穗正，苏光辉（2019）. 铅基快堆关键热工水力问题研究综述. 《原子能科学技术》.
689. 尹莎莎，方华伟，秋穗正，黄伟，陈志辉，田野，田雅婧（2019）. 模块化小型核反应堆自动卸压系统分析研究. 《原子能科学技术》.
690. 田文喜，张亚培，陈荣华，秋穗正，苏光辉（2018）. 西安交通大学核电厂系统与设备课程教学研究与实践. 《大学教育》.
691. 桂民洋，田文喜，吴迪，陈荣华，苏光辉，秋穗正（2018）. 子通道程序与CFD程序的耦合方法研究. 《原子能科学技术》.
692. 魏诗颖，田永红，吴荣，王成龙，田文喜，秋穗正，苏光辉（2018）. 铅铋-水直接接触沸水快堆系统子通道耦合热工分析. 《原子能科学技术》.
693. 张蕊，田文喜，秋穗正，苏光辉（2018）. 基于CFD方法的棒束通道内临界热流密度预测. 《原子能科学技术》.
694. 刘芳，张亚培，田文喜，苏光辉，秋穗正（2018）. 椭球形与球形下封头压力容器内熔融物滞留传热特性分析. 《原子能科学技术》.
695. 伍振兴，巫英伟，唐思邈，刘镝，秋穗正，苏光辉，田文喜（2018）. 随机填充球床通道内氦气流动特性实验研究. 《原子能科学技术》.
696. 李晨曦，文彦，郭凯伦，陈荣华，巫英伟，田文喜，秋穗正，苏光辉（2018）. 基于FOCUS程序的ADS颗粒流靶熔化事故分析. 《原子能科学技术》.
697. 秦浩，王成龙，张大林，田文喜，秋穗正，苏光辉（2018）. 氟盐冷却高温堆氚输运特性数值研究. 《原子能科学技术》.
698. 魏诗颖，王成龙，田文喜，苏光辉，秋穗正（2018）. 熔盐冷却球床实验堆内流动与传热特性数值研究. 《核动力工程》.
699. 孙浩，王成龙，刘逍，田文喜，秋穗正，苏光辉（2018）. 水下航行器微型核电源堆芯设计. 《原子能科学技术》.
700. 许芝春，张亚培，苏光辉，秋穗正，田文喜（2018）. 严重事故条件下安全壳响应模拟研究. 《原子能科学技术》.
701. 连强，刘镝，田文喜，秋穗正，苏光辉（2018）. 基于RELAP5的运动条件下并联双通道流动不稳定性研究. 《原子能科学技术》.
702. 邓阳斌，贺亚男，巫英伟，田文喜，秋穗正，苏光辉（2018）. 多层结构包壳和非刚体芯块力学建模及应用. 《原子能科学技术》.
703. 秦浩，王成龙，秋穗正，田文喜，苏光辉（2018）. 氟盐冷却高温堆氚输运特性瞬态分析. 《原子能科学技术》.
704. 刘逍，张文文，王成龙，张大林，田文喜，秋穗正，苏光辉（2018）. 空间堆辐射散热器设计分析. 《原子能科学技术》.
705. 魏诗颖，王成龙，苏光辉，田文喜，秋穗正（2018）. 铅铋冷却沸水快堆热工水力系统安全分析程序开发. 《核动力工程》.
706. 郑美银，陈平，张大林，田文喜，苏光辉，秋穗正（2018）. 钠冷驻波堆堆芯概念设计研究. 《核动力工程》.
707. Kun Zhang, Yu Hou, Wenxi Tian, Y.P. Zhang, G.H. Su, Suizheng Qiu (2018). Experimental investigations on single-phase convection and two-phase flow boiling heat transfer in an inclined rod bundle. Applied Thermal Engineering.DOI
708. Tangtao Feng, Wenxi Tian, Ping Song, Jun Wang, Mingjun Wang, Longze Li, G.H. Su, Suizheng Qiu (2018). Spatial temperature distribution of fuel assembly pre-simulation for a new simple core degradation experiment. Progress in Nuclear Energy.DOI
709. Liu Wang, Yandong Hou, Leitai Shi, Yingwei Wu, Wenxi Tian, Song Dekuan, Suizheng Qiu, G.H. Su (2018). Experimental study and optimized design on electromagnetic pump for liquid sodium. Annals of Nuclear Energy.DOI
710. Kailun Guo, Ronghua Chen, Suizheng Qiu, Wenxi Tian, G.H. Su (2018). An improved Multiphase Moving Particle Semi-implicit method in bubble rising simulations with large density ratios. Nuclear Engineering and Design.DOI
711. Ping Song, Dalin Zhang, Tangtao Feng, Shibao Wang, Jing Chen, Xinan Wang, Xiuli Xue, Yapei Zhang, Mingjun Wang, Suizheng Qiu, G.H. Su (2018). Numerical approach to study the thermal-hydraulic characteristics of Reactor Vessel Cooling system in sodium-cooled fast reactors. Progress in Nuclear Energy.DOI
712. Minghao Liu, Dalin Zhang, Chenglong Wang, Suizheng Qiu, G.H. Su, Wenxi Tian (2018). Experimental study on heat transfer performance between fluoride salt and heat pipes in the new conceptual passive residual heat removal system of molten salt reactor. Nuclear Engineering and Design.DOI
713. Limin Liu, Dalin Zhang, Linfeng Li, Yicheng Yang, Chenglong Wang, Suizheng Qiu, G.H. Su (2018). Experimental investigation of flow and convective heat transfer on a high-Prandtl-number fluid through the nuclear reactor pebble bed core. Applied Thermal Engineering.DOI
714. Qiang Lian, Wenxi Tian, Suizheng Qiu, G.H. Su (2018). Improvement of RELAP5 code for density wave instability analysis in parallel narrow rectangular channels. Annals of Nuclear Energy.DOI
715. Mingjun Wang, Di Fang, Yan Xiang, Fei Yi, Yun Wang, Wuyue Ren, Wenxi Tian, G.H. Su, Suizheng Qiu (2018). Study on the coolant mixing phenomenon in a 45° T junction based on the thermal-mechanical coupling method. Applied Thermal Engineering.DOI
716. Yangbin Deng, Yingwei Wu, Dalin Zhang, Wenxi Tian, G.H. Su, Suizheng Qiu (2018). Simulation on Pellet–Cladding Mechanical Interaction of Accident Tolerant Fuel With Coated Cladding. Journal of Nuclear Engineering and Radiation Science.DOI
717. Kailun Guo, Ronghua Chen, Yonglin Li, Wenxi Tian, G.H. Su, Suizheng Qiu (2018). Numerical simulation of Rayleigh-Taylor Instability with periodic boundary condition using MPS method. Progress in Nuclear Energy.DOI
718. Zhenxing Wu, Yingwei Wu, Simiao Tang, Di Liu, Suizheng Qiu, G.H. Su, Wenxi Tian (2018). DEM-CFD simulation of helium flow characteristics in randomly packed bed for fusion reactors. Progress in Nuclear Energy.DOI
719. Zehua Ma, Yingwei Wu, G.H. Su, Wenxi Tian, Suizheng Qiu (2018). Numerical and Experimental Investigation on Core Assembly Thermal-Gradient-Induced Deformation of Sodium-Cooled Fast Reactor.DOI
720. Limin Liu, Dalin Zhang, Linfeng Li, Yichen Yang, Chenglong Wang, Suizheng Qiu (2018). Experimental Studies on the Thermal-Hydraulics of Dowtherm A Through the Pebble Bed With Internal Heat Generation.DOI
721. Xiaohan Zhao, Mingjun Wang, Wenxi Tian, G.H. Su, Suizheng Qiu (2018). Hydraulic Characteristics Research on SG Under Tube Plugging Operations Using FLUENT.DOI
722. Jian Song, Yingwei Wu, Wenxi Tian, Suizheng Qiu, G.H. Su (2018). Characterization and Experimental Investigation for the Dynamic Performance of the Hydraulically Suspended Passive Shutdown System in China Sodium-Cooled Fast Reactor.DOI
723. Jing Chen, Dalin Zhang, Suizheng Qiu, Kui Zhang, Mingjun Wang, G.H. Su (2018). CFD Investigation of Thermal-Hydraulic Behaviors in Full Reactor Core for Sodium-Cooled Fast Reactor.DOI
724. Nina Yue, Rong Cai, Yun Wang, Suizheng Qiu, Dalin Zhang (2018). The Choose of Decay Heat Removal Systems of SFR.DOI
725. Shijie Cui, Dalin Zhang, Wenxi Tian, G.H. Su, Suizheng Qiu (2018). Conceptual Design and Neutronics/Thermal-Hydraulic Coupling Optimization Analyses of Two Typical Helium Cooled Solid Breeder Blanket Modules for CFETR Phase II.DOI
726. Ping Song, Dalin Zhang, Tangtao Feng, Shibao Wang, Yapei Zhang, Mingjun Wang, Suizheng Qiu, G.H. Su (2018). Development and Basic Verification of Decay Heat Removal Analysis Code of Sodium-Cooled Fast Reactor.DOI
727. Yandong Hou, Liu Wang, Yingwei Wu, Wenxi Tian, Suizheng Qiu, G.H. Su (2018). Pressure Drop Experiments of Liquid Sodium Flowing in a 7-Rod Bundle.DOI
728. Hao Yu, Mingjun Wang, Suizheng Qiu, Wenxi Tian, G.H. Su (2018). Development of Boron Dilution Model in COBRA-EN.DOI
729. Kailun Guo, Ronghua Chen, Suizheng Qiu, Wenxi Tian, G.H. Su, Junmei Wu (2018). Optimization of Moving Particle Semi-Implicit (MPS) Method and Studying of Flow Instability.DOI
730. Yongjun Wang, Kuanghan Deng, J M Wu, Nina Yue, Yuanfeng Zan, G.H. Su, Suizheng Qiu (2018). Experimental Study on the Critical Heat Flux of Nanofluid Flow Boiling Under Different Conditions.DOI
731. Simiao Tang, Chenglong Wang, G.H. Su, Suizheng Qiu, Wenxi Tian (2018). Thermal-Hydraulic Analysis of TOPAZ-II With Modified RELAP5.DOI
732. Shibao Wang, Dalin Zhang, Chenglong Wang, Ping Song, Jing Chen, Suizheng Qiu, G.H. Su (2018). Validation of a Code and Effect of Turbulence Model on Predicting Thermal Stratification Phenomena in the Upper Plenum of SFR.DOI
733. Siyang Huang, Xiaoyan Wang, Wenxi Tian, Ronghua Chen, Junmei Wu, G.H. Su, Suizheng Qiu (2018). Study on the Prediction of DNB-Type Critical Heat Flux in Rod Bundle Under Motion Conditions.DOI
734. Qiqi Yan, Simin Luo, Yapei Zhang, Limin Liu, G.H. Su, Suizheng Qiu (2018). Transient Thermal Behaviors of SBO Accident for a 200MW OFNP Under Heaving Motion Conditions.DOI
735. Tangtao Feng, Wenxi Tian, Ping Song, Jun Wang, Mingjun Wang, G.H. Su, Suizheng Qiu (2018). Numerical Research on Fuel Rod Progression During Core Degradation Process Using MELCOR.DOI
736. Rulei Sun, Yichen Yang, Dalin Zhang, Jiawei Bian, Suizheng Qiu, G.H. Su (2018). Study on Thermal-Hydraulic Characteristics of Vertical Narrow Rectangular Channel With Large Aspect Ratio Under Transverse Uneven Heating.DOI
737. Xianmao Wang, Yonggang Shen, Jiang Yang, Yong Ouyang, Rui Min, Suizheng Qiu (2018). Study of the Behaviors of an Open-Loop Heat-Removal System.DOI
738. Xiaoyan Wang, Siyang Huang, Wenxi Tian, Lie Chen, Suizheng Qiu, G.H. Su (2018). Effect of Rolling Motion on Flow Instability of Parallel Rectangular Channels of Natural Circulation.DOI
739. Liang Bo Hu, Kui Ge, Yapei Zhang, G.H. Su, Wenxi Tian, Suizheng Qiu (2018). Experimental Research on Energy Release and Fragments Characteristics Under Molten Materials Discharged Into Liquid Sodium.DOI
740. Hao Qin, Chenglong Wang, Suizheng Qiu, Dalin Zhang, Wenxi Tian, G.H. Su (2018). Tritium Transport Characteristics Analysis in Molten Salt Reactor Under Transient Conditions.DOI
741. Kuanghan Deng, Yi Zhang, C. L. Wang, Y. P. Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su, Yongjun Wang (2018). Experimental Investigation on Critical Heat Flux From Downward-Facing Flat Plate for Different Orientation Angles.DOI
742. Simin Luo, Xinan Wang, Yapei Zhang, Dalin Zhang, Suizheng Qiu, G.H. Su (2018). Numerical Research on Melt Pool Flow Characteristics Under Rolling Condition.DOI
743. Y. Xiang, Yingwei Wu, Mingjun Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2018). Experimental Investigation and Model Analysis on Upper Plenum Entrainment in AP1000.DOI
744. Yukun Zhou, Yapei Zhang, Simin Luo, Zhichun Xu, Luteng Zhang, Suizheng Qiu, G.H. Su (2018). COPRA Experiments on Melt Pool Behavior With Eutectic NaNO3-KNO3 Simulant.DOI
745. Jiawei Bian, Dalin Zhang, Rulei Sun, Yingwei Wu, Wenxi Tian, G.H. Su, Suizheng Qiu (2018). Experimental Study on Spray Pattern of Pressure-Swirl Nozzle in Reactor Containment.DOI
746. Hao Sun, Chenglong wang, Pan Ma, Xiao Liu, Wenxi Tian, Suizheng Qiu, Guanghui Su (2018). Conceptual design and analysis of a multipurpose micro nuclear reactor power source. Annals of Nuclear Energy.DOI
747. Shiying Wei, Chenglong Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2018). Transient thermal-hydraulic evaluation of lead-bismuth fast reactor by coupling sub-channel and system analysis codes. Nuclear Engineering and Design.DOI
748. Shibao Wang, Dalin Zhang, Ping Song, Yapei Zhang, Mingjun Wang, Yingwei Wu, Suizheng Qiu (2018). Validation of a methodology for thermal stratification analysis in sodium-cooled fast reactors. International Journal of Energy Research.DOI
749. Yukun Zhou, Y.P. Zhang, Simin Luo, Wenxi Tian, Suizheng Qiu, G.H. Su (2018). Results of simulant effect on large corium pool behavior based on COPRA facility. Progress in Nuclear Energy.DOI
750. Jian Ge, Wenxi Tian, Suizheng Qiu, G.H. Su (2018). CFD simulation of secondary side fluid flow and heat transfer of the passive residual heat removal heat exchanger. Nuclear Engineering and Design.DOI
751. Chenglong Wang, Hao Qin, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2018). Numerical study of tritium transport characteristics in Thorium Molten Salt Reactor with Solid Fuel (TMSR-SF). Nuclear Engineering and Design.DOI
752. Jiangtao Yu, Dalin Zhang, Leitai Shi, Wenxi Tian, G.H. Su, Suizheng Qiu (2018). Experimental investigation of entrainment effect on the countercurrent flow in the Hot Leg and Pressurizer Surge Line assembly of third-generation passive nuclear reactors. Nuclear Engineering and Design.DOI
753. Dalin Zhang, Ping Song, Shuang Wang, Xiaohua Wang, Jukai Chen, Liang Yu, Suizheng Qiu (2018). Analysis code development for the direct reactor auxiliary cooling system of the pool-type sodium-cooled fast reactor. Kerntechnik.DOI
754. Leitai Shi, G.H. Su, Jiangtao Yu, Chenglong Wang, Wenxi Tian, Suizheng Qiu (2018). Experimental investigation of the frictional pressure drop of steam-water two-phase flow in AP1000 surge line. Experimental Thermal and Fluid Science.DOI
755. Kun Zhang, Yu Hou, Wenxi Tian, Y.P. Zhang, G.H. Su, Suizheng Qiu (2018). Flow pattern effect on two-phase pressure drops in vertical upward flow across a horizontal tube bundle. Annals of Nuclear Energy.DOI
756. Y.P. Zhang, Kun Zhang, Jun Wang, G.H. Su, Wenxi Tian, Suizheng Qiu (2018). Research on pressure drop characteristics in inverted half U-tube bundle under two-phase cross-flow condition. Annals of Nuclear Energy.DOI
757. Di Liu, Wenxi Tian, Mengmeng Xi, Ronghua Chen, Suizheng Qiu, G.H. Su (2018). Study on safety boundary of flow instability and CHF for parallel channels in motion. Nuclear Engineering and Design.DOI
758. Guojun Yu, Chaofei Jiang, Liu Wang, G.H. Su, Suizheng Qiu (2018). A new method on fluid-to-fluid scaling for heat transfer in tubes at supercritical pressures. International Journal of Heat and Mass Transfer.DOI
759. Shasha Yin, Yajing Tian, Suizheng Qiu, Ye Tian, Huawei Fang, Wei Huang, Zhihui Chen (2018). Accident Process and Core Thermal Response During a Station Blackout Initiated Study for Small Modular Reactor. Frontiers in Energy Research.DOI
760. Nina Yue, Dalin Zhang, Jing Chen, Ping Song, Xinan Wang, Shibao Wang, Suizheng Qiu, G.H. Su, Yapei Zhang (2018). The development and validation of the inter-wrapper flow model in sodium-cooled fast reactors. Progress in Nuclear Energy.DOI
761. Simin Luo, Yapei Zhang, Yukun Zhou, Wenxi Tian, GH Su, Suizheng Qiu (2018). COPRA experiment and numerical research on the behavior of internally-heated melt pool with eutectic salt. Applied Thermal Engineering.DOI
762. Yongzheng Chen, Yingwei Wu, Mingjun Wang, Y.P. Zhang, Bing Tan, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2018). Development of a multi-compartment containment code for advanced PWR plant. Nuclear Engineering and Design.DOI
763. Mingjun Wang, Annalisa Manera, Victor Petrov, Suizheng Qiu, Wenxi Tian, G.H. Su (2018). Numerical Study of Integral Inherently Safe Light Water Reactor in Case of Inadvertent DHR Operation Based on the Multiscale Method. Nuclear Technology.DOI
764. Yangbin Deng, Yingwei Wu, Cheng Gong, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2018). Upgrade of FROBA code and its application in thermal-mechanical analysis of space reactor fuel. Nuclear Engineering and Design.DOI
765. Chenglong Wang, Shiying Wei, Wenxi Tian, Suizheng Qiu, G.H. Su (2018). Sub-channel analysis for Pb-Bi-cooled direct contact boiling water fast reactor. International Journal of Energy Research.DOI
766. Hao Sun, Chenglong Wang, Xiao Liu, Wenxi Tian, Suizheng Qiu, G.H. Su (2018). Reactor Core Design and Analysis for a Micronuclear Power Source. Frontiers in Energy Research.DOI
767. Leitai Shi, Bing Tan, Chenglong Wang, Wenxi Tian, Suizheng Qiu, Junmei Wu, G.H. Su (2018). Experimental investigation of gas lift pump in a lead-bismuth eutectic loop. Nuclear Engineering and Design.DOI
768. Juanli Zuo, Wenxi Tian, Suizheng Qiu, G.H. Su (2018). Transient safety analysis for simplified accelerator driven system with gas-lift pump. Progress in Nuclear Energy.DOI
769. Jiangtao Yu, Dalin Zhang, Leitai Shi, Zhiwei Wang, Wenxi Tian, G.H. Su, Suizheng Qiu (2018). Experimental research on the characteristics of steam-water counter-current flow in the Pressurizer Surge Line assembly. Experimental Thermal and Fluid Science.DOI
770. Kun Zhang, Yandong Hou, Wenxi Tian, Y.P. Zhang, G.H. Su, Suizheng Qiu (2018). Experimental investigation on steam-water two-phase flow boiling heat transfer in a staggered horizontal rod bundle under cross-flow condition. Experimental Thermal and Fluid Science.DOI
771. Ronghua Chen, Kailun Guo, Yanshi Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2018). Numerical analysis of the granular flow and heat transfer in the ADS granular spallation target. Nuclear Engineering and Design.DOI
772. Yun Wang, Kuanghan Deng, Junmei Wu, G.H. Su, Suizheng Qiu (2018). The characteristics and correlation of nanofluid flow boiling critical heat flux. International Journal of Heat and Mass Transfer.DOI
773. Mingjun Wang, Yan Xiang, Shijie Cui, Di Liu, Wenxi Tian, Dalin Zhang, Suizheng Qiu, G.H. Su (2018). Numerical study on the purge gas flow and heat transfer characteristics in helium cooled solid breeder blanket of CFETR. Progress in Nuclear Energy.DOI
774. Dalin Zhang, Limin Liu, Minghao Liu, Rongshuan Xu, Cheng Gong, Jun Zhang, Chenglong Wang, Suizheng Qiu, G.H. Su (2018). Review of conceptual design and fundamental research of molten salt reactors in China. International Journal of Energy Research.DOI
775. Minghao Liu, Dalin Zhang, Chenglong Wang, Suizheng Qiu, G.H. Su, Wenxi Tian (2018). Experimental study on the heat transfer characteristics of fluoride salt in the new conceptual passive heat removal system of molten salt reactor. International Journal of Energy Research.DOI
776. Shijie Cui, Dalin Zhang, Wenxi Tian, G.H. Su, Suizheng Qiu (2018). Numerical research on the coupling optimization design rule of the CFETR HCSB blanket using the NTCOC code. Fusion Engineering and Design.DOI
777. Rulei Sun, Dalin Zhang, Liang Yu, Mingjun Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2018). Development of a subchannel analysis code for SFR wire-wrapped fuel assemblies. Progress in Nuclear Energy.DOI
778. Yanan He, Chen Ping, Yingwei Wu, G.H. Su, Wenxi Tian, Suizheng Qiu (2018). Preliminary evaluation of U3Si2-FeCrAl fuel performance in light water reactors through a multi-physics coupled way. Nuclear Engineering and Design.DOI
779. Yonglin Li, Ronghua Chen, Wenxi Tian, Suizheng Qiu, G.H. Su (2018). Numerical Investigation of Dissolution Reaction between UO2 and Molten Zry-4 using MPS method. Proceeding of Second Thermal and Fluids Engineering Conference.DOI
780. 刘镝，田文喜，秋穗正，苏光辉，王艳林，刘文兴，袁德文，黄彦平（2017）. 运动条件下自然循环工况并联通道流动不稳定性程序初步开发及验证. 《第十五届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室学术年会论文集》.
781. 桂民洋，刘镝，田文喜，陈荣华，秋穗正，苏光辉（2017）. 基于VIPRE的运动条件下子通道分析程序开发. 《第十五届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室学术年会论文集》.
782. 李勇霖，陈荣华，田文喜，秋穗正，苏光辉（2017）. 基于MPS方法的共晶反应研究. 《第十五届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室学术年会论文集》.
783. 孙洪平，张亚培，田文喜，苏光辉，秋穗正（2017）. CPR1000核电厂全厂断电事故及安全注射系统缓解能力研究. 《第十五届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室学术年会论文集》.
784. 向延，王明军，巫英伟，田文喜，秋穗正，苏光辉（2017）. AP1000上腔室夹带模型研究. 《第十五届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室学术年会论文集》.
785. 张大林，岳倪娜，宋苹，陈静，王式保，王心安，秋穗正（2017）. 快堆直接热交换器布置方式对事故余热排出特性的影响研究. 《第十五届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室学术年会论文集》.
786. 王云，邓匡汉，武俊梅，苏光辉，秋穗正（2017）. 纳米流体竖直管内流动沸腾CHF实验研究. 《第十五届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室学术年会论文集》.
787. 岳倪娜，黄思洋，曹念，秋穗正，周磊（2017）. 起伏条件对强迫循环和自然循环系统特性的影响. 《第十五届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室学术年会》.
788. 魏诗颖，王成龙，田永红，田文喜，秋穗正，苏光辉（2017）. 铅铋-水直接接触沸水快堆(PBWFR)系统-子通道耦合热工分析. 《第十五届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室学术年会论文集》.
789. 秦浩，王成龙，张大林，田文喜，秋穗正，苏光辉（2017）. 氟盐冷却高温堆氚输运特性分析程序开发. 《第十五届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室学术年会论文集》.
790. 黄涛，高颖贤，钟明君，吴丹，苏光辉，秋穗正（2017）. 全场断电叠加小破口事故下氢气爆炸研究. 《中国核学会2017年学术年会》.
791. 杨红发，巫英伟，田文喜，苏光辉，秋穗正（2017）. 大破口事故下事故容错燃料安全性能分析. 《第十五届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室学术年会》.
792. 孙浩，王成龙，刘逍，田文喜，秋穗正，苏光辉（2017）. 水下航行器微型核电源堆芯初步设计. 《第十五届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室学术年会》.
793. 王式保，张大林，宋苹，陈静，王心安，秋穗正（2017）. 池式钠冷快堆二维钠池热工水力分析程序开发. 《第十五届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室学术年会论文集》.
794. 张俊，张大林，王成龙，田文喜，秋穗正，苏光辉（2017）. 基于MCNP和ORIGEN的熔盐快堆燃耗分析计算. 《原子能科学技术》.
795. 张文文，刘逍，田文喜，秋穗正，苏光辉（2017）. 兆瓦级空间热管反应堆动力系统概念设计. 《原子能科学技术》.
796. 魏诗颖，王玮，王成龙，田文喜，秋穗正，苏光辉（2017）. TACR热传输系统热工水力瞬态分析. 《核技术》.
797. 宋健，谭超，唐思邈，刘利民，田文喜，巫英伟，秋穗正，苏光辉（2017）. 基于RELAP5 MOD3.2的钠冷快堆热工水力系统分析程序开发及验证. 《原子能科学技术》.
798. 黄涛，高颖贤，丁书华，钟明君，吴丹，苏光辉，秋穗正（2017）. 三维氢气爆炸分析程序的开发及初步验证. 《原子能科学技术》.
799. 胡亮，张亚培，苏光辉，田文喜，秋穗正（2017）. 基于DEM的重金属颗粒流靶区输运过程研究. 《原子能科学技术》.
800. 张文文，王成龙，田文喜，秋穗正，苏光辉，赵小林，刘汉刚（2017）. 新型热管反应堆堆芯热工安全分析. 《原子能科学技术》.
801. 许荣栓，刘利民，王宁，张大林，王成龙，秋穗正，苏光辉（2017）. 基于修改后RELAP5/MOD3.2的氟盐高温堆实验回路分析. 《原子能科学技术》.
802. 任五岳，汪刘，于国军，边嘉伟，田文喜，苏光辉，秋穗正（2017）. T型管直接接触冷凝特性实验研究. 《原子能科学技术》.
803. 仇子铖，兰治科，秋穗正，谢旭，鲁晓东，孙都成（2017）. 环形通道内液态金属钠沸腾两相传热特性实验研究. 《原子能科学技术》.
804. 田文喜，蔚江涛，汪志伟，苏光辉，秋穗正（2017）. AP1000波动管内空气-水液泛特性试验研究. 《核动力工程》.
805. 王成龙，胡玲文，秋穗正，苏光辉，田文喜（2017）. 可移动式熔盐冷却高温堆(TFHR)热工水力特性不确定性分析. 《核动力工程》.
806. 冯唐涛，田文喜，宋苹，张大林，苏光辉，秋穗正（2017）. 基于耦合程序的流体瞬变流动水锤现象分析. 《原子能科学技术》.
807. 仇子铖，兰治科，秋穗正，高新力，鲁晓东，孙都成（2017）. 环形通道内液态金属钠沸腾两相流动特性实验研究. 《原子能科学技术》.
808. 任五岳，田文喜，边嘉伟，于国军，汪刘，苏光辉，秋穗正（2017）. T型管热混合温度波动特性研究. 《原子能科学技术》.
809. 伍振兴，阎昌琪，田春平，田旺盛，秋穗正（2017）. 自然循环与强迫循环条件下阻力及换热特性对比. 《原子能科学技术》.
810. Jing Chen, Dalin Zhang, Ping Song, Xinan Wang, Shibao Wang, Liang Yu, Suizheng Qiu, Yapei Zhang, Mingjun Wang, G.H. Su (2017). CFD investigation on thermal-hydraulic behaviors of a wire-wrapped fuel subassembly for sodium-cooled fast reactor. Annals of Nuclear Energy.DOI
811. J. Zhang, R.H. Chen, Mingjun Wang, Wenxi Tian, Yingwei Wu, G.H. Su, Suizheng Qiu (2017). A code development for leak before break (LBB) leakage from supercritical to subcritical conditions. Progress in Nuclear Energy.DOI
812. Yingwei Wu, Simin Luo, Liu Wang, Yandong Hou, G.H. Su, Wenxi Tian, Suizheng Qiu (2017). Review on heat transfer and flow characteristics of liquid sodium (2): Two-phase. Progress in Nuclear Energy.DOI
813. Jian Ge, Wenxi Tian, Suizheng Qiu, G.H. Su (2017). CFD investigation on thermal hydraulics of the passive residual heat removal heat exchanger (PRHR HX). Nuclear Engineering and Design.DOI
814. Chaofei Jiang, Guojun Yu, Wenxi Tian, Suizheng Qiu, G.H. Su (2017). Development of safety analysis code for SCWR and its LOCA analysis of CSR1000. Nuclear Engineering and Design.DOI
815. Zhenhui Ma, Yuzhou Lu, Ronghua Chen, Hang Xiao, Mingjun Wang, G.H. Su, Suizheng Qiu, Wenxi Tian (2017). Study on the hydrogen risk in venturi scrubber filter of filtered containment venting system under PWR severe accident. Nuclear Engineering and Design.DOI
816. Hao Qin, Chenglong Wang, Suizheng Qiu, Dalin Zhang, Wenxi Tian, G.H. Su (2017). Study of tritium transport characteristics in a transportable fluoride-salt-cooled high-temperature reactor. International Journal of Energy Research.DOI
817. Bing Tan, Yingwei Wu, Y. Xiang, Yongzheng Chen, Leishi Tai, Wenxi Tian, Suizheng Qiu, G.H. Su (2017). Experimental investigation on hot water seal over an analogous U-shaped device. Experimental Thermal and Fluid Science.DOI
818. Limin Liu, Dalin Zhang, Jian Song, Chenglong Wang, Xinli Gao, Wenxi Tian, Suizheng Qiu, G.H. Su (2017). Modification and application of Relap5 Mod3 code to several types of nonwater-cooled advanced nuclear reactors. International Journal of Energy Research.DOI
819. Yingwei Wu, Yandong Hou, Liu Wang, Simin Luo, G.H. Su, Wenxi Tian, Suizheng Qiu (2017). Review on heat transfer and flow characteristics of liquid sodium (1): Single-phase. Progress in Nuclear Energy.DOI
820. Shijie Cui, Dalin Zhang, Xinli Gao, Wenxi Tian, G.H. Su, Suizheng Qiu (2017). Conceptual design and comprehensive optimization analysis of a fusion-fission hybrid reactor water-cooled pressure tube blanket. Progress in Nuclear Energy.DOI
821. Shijie Cui, Dalin Zhang, Jian Ge, Jie Cheng, Wenxi Tian, G.H. Su, Suizheng Qiu (2017). Development and application of a neutronics/thermal-hydraulics coupling optimization code for the CFETR helium cooled solid breeder blanket with mixed pebble beds. Fusion Engineering and Design.DOI
822. J. Zhang, R.H. Chen, Mingjun Wang, Wenxi Tian, G.H. Su, Suizheng Qiu (2017). Prediction of LBB leakage for various conditions by genetic neural network and genetic algorithms. Nuclear Engineering and Design.DOI
823. Zhenhui Ma, Ronghua Chen, Maolin Tian, Jian Song, Dalin Zhang, G.H. Su, Xiaorong Li, Linglan Zhou, Suizheng Qiu (2017). Analysis of flow blockage accidents in rectangular fuel assembly based on CFD methodology. Annals of Nuclear Energy.DOI
824. Chenglong Wang, Kaichao Sun, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2017). Thermal-hydraulic design and analysis of a small modular molten salt reactor (MSR) with solid fuel. International Journal of Energy Research.DOI
825. Luteng Zhang, Simin Luo, Yapei Zhang, Wenxi Tian, G.H. Su, Suizheng Qiu (2017). Large eddy simulation on turbulent heat transfer in reactor vessel lower head corium pools. Annals of Nuclear Energy.DOI
826. Di Liu, Wenxi Tian, G.H. Su, Suizheng Qiu (2017). Experimental study on helium pressure drop across randomly packed bed for fusion blanket. Fusion Engineering and Design.DOI
827. Chenglong Wang, Kaichao Sun, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2017). Uncertainty analysis of Transportable Fluoride-salt-cooled High-temperature Reactor (TFHR) using coupled DAKOTA with RELAP-3D method. Nuclear Engineering and Design.DOI
828. Shiying Wei, Chenglong Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2017). Thermal hydraulic design and analysis of Thorium-based Advanced CANDU Reactor (TACR). Nuclear Engineering and Design.DOI
829. Shijie Cui, Dalin Zhang, Qiang Lian, Wenxi Tian, Jie Cheng, G.H. Su, Suizheng Qiu (2017). Development of a neutronics/thermal-hydraulic coupling optimization code and its application on the CFETR HCSB blanket. Fusion Engineering and Design.DOI
830. Mingjun Wang, Lianfa Wang, Jianping Jing, Xinli Gao, Suizheng Qiu, Wenxi Tian, G.H. Su (2017). Study on the reactor core barrel instantaneous characteristics in case of Loss of Coolant Accident (LOCA) scenarios for loop-type PWR. Nuclear Engineering and Design.DOI
831. Dalin Zhang, Limin Liu, Minghao Liu, Rongshuan Xu, Cheng Gong, Suizheng Qiu (2017). Neutronics/Thermal-hydraulics Coupling Analysis for the Liquid-Fuel MOSART Concept. Energy Procedia.DOI
832. Shijie Cui, Dalin Zhang, Qiang Lian, Jie Cheng, Wenxi Tian, G.H. Su, Suizheng Qiu (2017). Evaluation and optimization of tritium breeding, shielding and nuclear heating performances of the helium cooled solid breeder blanket for CFETR. International Journal of Hydrogen Energy.DOI
833. Zhaoming Meng, Lei Ding, Zicheng Qiu, Zhongning Sun, Changqi Yan, Suizheng Qiu, G.H. Su, Wenxi Tian (2017). Model application research for liquid entrainment through ADS-4 pipe in AP1000. Annals of Nuclear Energy.DOI
834. Qiang Lian, Wenxi Tian, Shijie Cui, Suizheng Qiu, G.H. Su (2017). Preliminary safety assessment on two LOCAs under ITER-like condition for the optimized CFETR helium cooled solid breeder blanket. Fusion Engineering and Design.DOI
835. Liang Bo Hu, Yapei Zhang, G.H. Su, Wenxi Tian, Suizheng Qiu (2017). Numerical study on cooling characteristics in granular and liquid spallation targets. Nuclear Engineering and Design.DOI
836. Mingjun Wang, Di Liu, Yan Xiang, Shijie Cui, G.H. Su, Suizheng Qiu, Wenxi Tian (2017). Experimental study of the helium flow characteristics in pebble-bed under the condition of CFETR's blanket module. Progress in Nuclear Energy.DOI
837. Ronghua Chen, Chenxi Li, Wang Jun, G.H. Su, Suizheng Qiu, Michael L. Corradini (2017). Analysis of the dynamic pressure from ex-vessel steam explosion for pressurized water reactor. Progress in Nuclear Energy.DOI
838. Dalin Zhang, Jing Chen, Ping Song, Shibao Wang, Xin’an Wang, Linfeng Li, Suizheng Qiu, G.H. Su (2017). Theoretical and Experimental Research on the Single-Phase and Incipient Boiling Heat Transfer of Liquid Metal Sodium.DOI
839. Yangbin Deng, Bowen Qiu, Yingwei Wu, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2017). Simulation on Pellet-Cladding Mechanical Interaction (PCMI) of Accident Tolerant Fuel (ATF) With Coated Cladding.DOI
840. Jian Song, Limin Liu, Simiao Tang, Yingwei Wu, Wenxi Tian, Suizheng Qiu, G.H. Su (2017). Implementation of Liquid Metal Properties in RELAP5 MOD3.2 for Safety Analysis of Sodium-Cooled Fast Reactors.DOI
841. Jiangtao Yu, Dalin Zhang, Leitai Shi, Zhiwei Wang, Wenxi Tian, G.H. Su, Suizheng Qiu (2017). Experimental Study on the Steam-Water Co-Current Flow Friction Multiplier of the AP1000 Surge Line.DOI
842. Leitai Shi, G.H. Su, Bing Tan, Ronghua Chen, Wenxi Tian, Suizheng Qiu, Junmei Wu (2017). Experimental Study on Natural Circulation in a Lead Bismuth Eutectic Loop.DOI
843. Xi Wang, Yingwei Wu, Wenxi Tian, Suizheng Qiu, G.H. Su (2017). CFD Simulation of Thermal-Hydraulic Characteristics of Water Seal Structure in PWR Pressurizer.DOI
844. Jian Ge, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2017). Coupled Analysis of Thermal Hydraulics and Neutronics for a Molten Salt Reactor.DOI
845. Longze Li, Tae Woon Kim, Yapei Zhang, Shripad T. Revankar, Wenxi Tian, G.H. Su, Suizheng Qiu (2017). MELCOR severe accident analysis for a natural circulation small modular reactor. Progress in Nuclear Energy.DOI
846. Chenglong Wang, Limin Liu, Minghao Liu, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2017). Conceptual design and analysis of heat pipe cooled silo cooling system for the transportable fluoride-salt-cooled high-temperature reactor. Annals of Nuclear Energy.DOI
847. Yonglin Li, Ronghua Chen, Kailun Guo, Wenxi Tian, Suizheng Qiu, G.H. Su (2017). Numerical analysis of the dissolution of uranium dioxide by molten zircaloy using MPS method. Progress in Nuclear Energy.DOI
848. Tangtao Feng, Dalin Zhang, Ping Song, Wenxi Tian, Wei Li, G.H. Su, Suizheng Qiu (2017). Numerical research on water hammer phenomenon of parallel pump-valve system by coupling FLUENT with RELAP5. Annals of Nuclear Energy.DOI
849. Ronghua Chen, Yonglin Li, Kailun Guo, Wenxi Tian, Suizheng Qiu, G.H. Su (2017). Numerical investigation on the dissolution kinetics of ZrO 2 by molten zircaloy using MPS method. Nuclear Engineering and Design.DOI
850. Mingjun Wang, Leyuan Bai, Lianfa Wang, Suizheng Qiu, Wenxi Tian, G.H. Su (2017). Thermal hydraulic and stress coupling analysis for AP1000 Pressurized Thermal Shock (PTS) study under SBLOCA scenario. Applied Thermal Engineering.DOI
851. Chenglong Wang, Kaichao Sun, Lin-Wen Hu, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2017). Transient Safety Analysis of a Transportable Fluoride-Salt-Cooled High-Temperature Reactor Using RELAP5-3D. Nuclear Technology.DOI
852. Ronghua Chen, Maolin Tian, Sen Chen, Wenxi Tian, G.H. Su, Suizheng Qiu (2017). Three dimensional thermal hydraulic characteristic analysis of reactor core based on porous media method. Annals of Nuclear Energy.DOI
853. D.C. Sun, Y. Zhang, Suizheng Qiu, Yuanfeng Zan, Wenwei Liu, G.H. Su (2017). Models development of liquid drops entrainment at a T-junction with a large vertical up branch. International Journal of Heat and Mass Transfer.DOI
854. Maolin Tian, Tenglong Cong, Zhenhui Ma, Ronghua Chen, Wenxi Tian, Suizheng Qiu, G.H. Su (2017). A new unidentified leak detection method based on the EVR ventilation condensate. Progress in Nuclear Energy.DOI
855. Yangbin Deng, Yingwei Wu, Bowen Qiu, Dalin Zhang, Mingjun Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2017). Development of a new Pellet-Clad Mechanical Interaction (PCMI) model and its application in ATFs. Annals of Nuclear Energy.DOI
856. Kailun Guo, Ronghua Chen, Yonglin Li, Suizheng Qiu, G.H. Su (2017). Numerical investigation of the fluid-solid mixture flow using the FOCUS code. Progress in Nuclear Energy.DOI
857. Chenglong Wang, Jing Chen, Suizheng Qiu, Wenxi Tian, Dalin Zhang, G.H. Su (2017). Performance analysis of heat pipe radiator unit for space nuclear power reactor. Annals of Nuclear Energy.DOI
858. Ronghua Chen, Lie Chen, Kailun Guo, Akifumi Yamaji, Masahiro Furuya, Wenxi Tian, G.H. Su, Suizheng Qiu (2017). Numerical analysis of the melt behavior in a fuel support piece of the BWR by MPS. Annals of Nuclear Energy.DOI
859. Mingjun Wang, Qiaolin Zuo, Hao Yu, Wenxi Tian, G.H. Su, Suizheng Qiu (2017). Multiscale Thermal Hydraulic Study under the Inadvertent Safety Injection System Operation Scenario of Typical Pressurized Water Reactor. Science and Technology of Nuclear Installations.DOI
860. Kailun Guo, Ronghua Chen, Yonglin Li, Suizheng Qiu, G.H. Su (2017). Numerical Simulation of the Fluid-Solid Mixture Flow Based on the MPS method. Proceeding of Second Thermal and Fluids Engineering Conference.DOI
861. Guojun Yu, Wuyue Ren, Jiawei Bian, G.H. Su, Wenxi Tian, Suizheng Qiu (2017). EXPERIMENTAL STUDY ON VOID FRACTION OF ECCS TWO-PHASE FLOW. Proceeding of Second Thermal and Fluids Engineering Conference.DOI
862. Tang Simiao, Jian Song, Zhang Dalin, Wang Chenglong, Qiu Suizheng, Su Guanghui, Tian Wenxi (2017). Thermal-Hydraulic Analysis of the EBR-II SHRT-45R Unprotected Loss of Flow Experiment With Modified RELAP5.DOI
863. Zhenhua Wu, Changqi Yan, Chunping Tian, Wangsheng Tian, Qiu Suizheng (2017). Comparison of flow resistance and heat transfer characteristics under natural and forced circulations. Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms.DOI
864. 张文文，田文喜，秋穗正，苏光辉，赵小林，刘汉刚（2016）. 热管式空间反应堆堆芯热工安全分析. 《第十八届中国科协年会——分6 军民融合高端论坛》.
865. 王成龙，宋健，陈静，张文文，田文喜，苏光辉，张大林，秋穗正，刘天才，柴宝华（2016）. TOPAZ-Ⅱ改进型热管辐射换热器传热单元数值研究. 《原子能科学技术》.
866. 李沛颖，向延，孙都成，张大林，张鹏，秋穗正，苏光辉（2016）. AP1000 ADS-4夹带卸压试验模拟分析. 《原子能科学技术》.
867. 向延，孙都成，巫英伟，张鹏，秋穗正，苏光辉（2016）. AP1000上腔室夹带试验研究. 《原子能科学技术》.
868. 陈静，田文喜，苏光辉，张大林，巫英伟，秋穗正（2016）. 超临界流体管内对流换热模化分析. 《原子能科学技术》.
869. 黄涛，毛辉辉，张亚培，苏光辉，秋穗正（2016）. 局部空间内氢气爆炸程序开发及应用. 《原子能科学技术》.
870. 左巧林，秋穗正，王明军（2016）. 恰希玛核电厂压力容器各关键部位在PTS瞬态下的温度场研究. 《原子能科学技术》.
871. 张卢腾，马如冰，周瑜琨，张亚培，田文喜，秋穗正，苏光辉，马卫民，元一单（2016）. 高瑞利数下熔融池换热特性试验研究. 《原子能科学技术》.
872. 武小莉，汪洋，张亚培，田文喜，苏光辉，秋穗正，刘彤，任啟森，黄恒（2016）. 事故容错燃料在大破口事故下的安全分析. 《原子能科学技术》.
873. 张卢腾，张亚培，周瑜琨，田文喜，秋穗正，苏光辉，马卫民，赵博，元一单（2016）. 硬壳对熔融池换热特性影响试验研究. 《原子能科学技术》.
874. 张文文，陈荣华，田文喜，秋穗正，苏光辉（2016）. TOPAZ-Ⅱ系统启动过程模拟. 《原子能科学技术》.
875. 张文文，陈静，田文喜，秋穗正，苏光辉（2016）. TOPAZ-Ⅱ空间电源系统辐射器改进研究. 《原子能科学技术》.
876. 仇子铖，兰治科，马在勇，秋穗正，昝元峰，幸奠川，李永亮（2016）. 液态金属钠沸腾两相流动传热特性理论研究. 《核动力工程》.
877. 戈剑，丛腾龙，张文文，田文喜，秋穗正，苏光辉（2016）. 自然对流条件下PRHEHX传热特性数值研究. 《核动力工程》.
878. 李伟，苏光辉，秋穗正，田文喜，陈平，李垣明（2016）. 一种稳定性增强及高精度数值方法在RELAP5中的实现与评价. 《核技术》.
879. Wuyue Ren, Guojun Yu, Jiawei Bian, Wang Liu, Wenxi Tian, G.H. Su, Suizheng Qiu, Qiao Wu (2016). Experiment research on thermal mixing in horizontal T-junction: In-pipe temperature and flow characteristic research. Progress in Nuclear Energy.DOI
880. Limin Liu, Dalin Zhang, Qiqi Yan, Rongshuan Xu, Chenglong Wang, Suizheng Qiu, G.H. Su (2016). RELAP5 MOD3.2 modification and application to the transient analysis of a fluoride-salt-cooled high-temperature reactor. Annals of Nuclear Energy.DOI
881. Yangbin Deng, Yingwei Wu, Dalin Zhang, Qing Gang Lu, Wenxi Tian, Suizheng Qiu, G.H. Su (2016). Thermal-mechanical coupling behavior analysis on metal-matrix dispersed plate-type fuel. Progress in Nuclear Energy.DOI
882. Chaofei Jiang, Wenxi Tian, Suizheng Qiu, G.H. Su (2016). Development of Safety Analysis Code TACOS and Application to Fuel Qualification Test Loop. Journal of Nuclear Engineering and Radiation Science.DOI
883. Jiangtao Yu, Dalin Zhang, Leitai Shi, Zhiwei Wang, Shixian Yan, Bo Dong, Wenxi Tian, G.H. Su, Suizheng Qiu (2016). Experimental Investigation of Air-Water CCFL in the Pressurizer Surge Line of AP1000. Nuclear Technology.DOI
884. Ronghua Chen, Jun Wang, G.H. Su, Suizheng Qiu, Michael L. Corradini (2016). Analysis of KROTOS KS-2 and KS-4 steam explosion experiments with TEXAS-VI. Nuclear Engineering and Design.DOI
885. Tangtao Feng, Mingjun Wang, Ping Song, Wenxi Tian, G.H. Su, Suizheng Qiu (2016). Thermal hydraulic characteristics analysis of direct residual heat removal system for China pressurized reactor. Progress in Nuclear Energy.DOI
886. Rong Cai, Nina Yue, Ronghua Chen, Wenxi Tian, G.H. Su, Suizheng Qiu (2016). Development of a thermal-hydraulic subchannel analysis code for motion conditions. Progress in Nuclear Energy.DOI
887. Kun Zhang, Yandong Hou, Wenxi Tian, Ya‐Ting Fan, G.H. Su, Suizheng Qiu (2016). Experimental investigations on single-phase convection and steam-water two-phase flow boiling in a vertical rod bundle. Experimental Thermal and Fluid Science.DOI
888. Wenwen Zhang, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2016). Thermal-hydraulic analysis of the improved TOPAZ-II power system using a heat pipe radiator. Nuclear Engineering and Design.DOI
889. Wenwen Zhang, Chenglong Wang, Ronghua Chen, Wenxi Tian, Suizheng Qiu, G.H. Su (2016). Preliminary design and thermal analysis of a liquid metal heat pipe radiator for TOPAZ-II power system. Annals of Nuclear Energy.DOI
890. Jun Wang, Chen Wang, Michael L. Corradini, Troy Haskin, Wenxi Tian, G.H. Su, Suizheng Qiu (2016). PHEBUS FPT-1 simulation by using MELCOR and primary blockage model exploration. Nuclear Engineering and Design.DOI
891. Wuyue Ren, Xiaoqi FU, Wenxi Tian, Bo Dong, Jiawei Bian, Guojun Yu, Yuzhe Yang, Suizheng Qiu, G.H. Su (2016). ECC condensation research in T-junction. Progress in Nuclear Energy.DOI
892. Yangbin Deng, Dalin Zhang, Qing Gang Lu, Yingwei Wu, Wenxi Tian, Suizheng Qiu, G.H. Su (2016). Mechanism Study and Numerical Simulation on Blistering of Plate-Type Fuel.DOI
893. Shijie Cui, Dalin Zhang, Jie Chang, Wenxi Tian, Suizheng Qiu, G.H. Su (2016). Thermo-Hydraulic Analysis of the Optimized Helium Cooled Solid Breeder Blanket for CFETR.DOI
894. Di Liu, Wenxi Tian, Suizheng Qiu, G.H. Su (2016). CFD Analysis of Cross Flow in Rod Bundles Under Rolling Motion.DOI
895. Ronghua Chen, Lie Chen, Wenxi Tian, G.H. Su, Suizheng Qiu (2016). Numerical Analysis of the Corium Behavior Within the Fuel Support Piece by MPS.DOI
896. Jie Cheng, Yingwei Wu, G.H. Su, Suizheng Qiu, Wenxi Tian (2016). Neutronics and Thermo-Hydraulic Analysis of Water-Cooled Blanket Based on PWR and SCWR Water Conditions for CFETR.DOI
897. Bing Tan, Yingwei Wu, Y. Xiang, Leitai Shi, Wenxi Tian, Suizheng Qiu, G.H. Su (2016). Experimental Investigation on Analogous U-Shaped Tube Water Seal in Front of Pressurizer Safety Valve.DOI
898. Y. Xiang, Yingwei Wu, Suizheng Qiu, Wenxi Tian, G.H. Su (2016). Experimental and Simulative Investigation of ADS-4 Depressurization Process in AP1000.DOI
899. Rong Cai, Siyang Huang, Kai Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2016). Development and Verification of Thermal Hydraulic Subchannel Analysis Code for Motion Conditions.DOI
900. Yapei Zhang, Luteng Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2016). Numerical Study on the Heat Transfer Characteristics of COPRA-L1 Melt Pool Based on the LES Method.DOI
901. Yongzheng Chen, Yingwei Wu, Wenxi Tian, Suizheng Qiu, G.H. Su (2016). Validation of the ATHROC Code With NUPEC Tests.DOI
902. Limin Liu, Qiqi Yan, Dalin Zhang, Suizheng Qiu, G.H. Su (2016). Investigation of the Modified RELAP5 MOD 3.2 Capability to Simulate the Transients of the Fluoride-Salt High-Temperature Reactors.DOI
903. Wenwen Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2016). Start-Up Simulation of the Improved TOPAZ-II Space Power System.DOI
904. Sufen Li, Suizheng Qiu, Quanhu Zhang, Yonggang Huo, Limin Liu (2016). Fast Neutron Multiplicity Simulation of Nuclear Material Based on Geant4.DOI
905. M.Y. Zheng, Wenxi Tian, Dalin Zhang, Suizheng Qiu, G.H. Su (2016). Performance of radial fuel shuffling sodium cooled Breed and Burn reactor core. Annals of Nuclear Energy.DOI
906. Kun Zhang, Wenxi Tian, Yu Hou, Y.P. Zhang, Suizheng Qiu, G.H. Su (2016). Pressure drop characteristics of vertically upward flow in inclined rod bundles. Experimental Thermal and Fluid Science.DOI
907. Y. Xiang, Yingwei Wu, D.C. Sun, Wenxi Tian, P. Zhang, Suizheng Qiu, G.H. Su (2016). Experimental simulation of liquid entrainment in ADS-4 depressurization line in AP1000. Progress in Nuclear Energy.DOI
908. Jian Ge, Chenglong Wang, Yao Xiao, Wenxi Tian, Suizheng Qiu, G.H. Su, Dalin Zhang, Yingwei Wu (2016). Thermal-hydraulic analysis of a fluoride-salt-cooled pebble-bed reactor with CFD methodology. Progress in Nuclear Energy.DOI
909. Ziyan Guo, Nicolas Zweibaum, Meiyue Shao, Lakshana Huddar, Per F. Peterson, Suizheng Qiu (2016). Development of the FHR advanced natural circulation analysis code and application to FHR safety analysis. Progress in Nuclear Energy.DOI
910. Mingjun Wang, Annalisa Manera, Suizheng Qiu, G.H. Su (2016). Ammonia-water mixture property code (AWProC) development, verification and Kalina cycle design for nuclear power plant. Progress in Nuclear Energy.DOI
911. Suizheng Qiu, Dalin Zhang, Limin Liu, M. Liu, Rongshuan Xu, C. Gong, G.H. Su (2016). Coupled neutronics/thermal-hydraulics and safety characteristics of liquid-fueled Molten Salt Reactors. Kerntechnik.DOI
912. Y.P. Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2016). Study effects of the kinetics of local composition diffusion on the melt pool coolability by developing a DBL-LIVE model. Progress in Nuclear Energy.DOI
913. Yangbin Deng, Yingwei Wu, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2016). Development of a thermal–mechanical behavior coupling analysis code for a dual-cooled annular fuel element in PWRs. Nuclear Engineering and Design.DOI
914. Tao Huang, Y.P. Zhang, Houjun Gong, Wenxi Tian, G.H. Su, Suizheng Qiu (2016). Development of the analysis tool for the water cooling type passive residual heat removal system of Chinese pressurized reactor. Progress in Nuclear Energy.DOI
915. Yangbin Deng, Yingwei Wu, Yuanming Li, Dalin Zhang, Wenxi Tian, G.H. Su, Suizheng Qiu (2016). Mechanism study and theoretical simulation on heat split phenomenon in dual-cooled annular fuel element. Annals of Nuclear Energy.DOI
916. Jun Wang, Yuqiao Fan, Yapei Zhang, Xinghe Ni, Wenxi Tian, Michael L. Corradini, G.H. Su, Suizheng Qiu (2016). The Development of Candling Module Code in Module In-vessel Degraded Analysis Code MIDAC and the Relevant Calculation for CPR1000 During Large-Break LOCA. Journal of Nuclear Engineering and Radiation Science.DOI
917. Kun Zhang, Ya‐Ting Fan, Wenxi Tian, Kailun Guo, Suizheng Qiu, G.H. Su (2016). Pressure drop characteristics of two-phase flow in a vertical rod bundle with support plates. Nuclear Engineering and Design.DOI
918. Chenglong Wang, Kaichao Sun, Lin-Wen Hu, Suizheng Qiu, G.H. Su (2016). Thermal-Hydraulic Analyses of Transportable Fluoride Salt–Cooled High-Temperature Reactor with CFD Modeling. Nuclear Technology.DOI
919. Jianfu Zhang, Xiaoping Ouyang, Xianpeng Zhang, Jinlu Ruan, Guoguang Zhang, Xiaodong Zhang, Suizheng Qiu, Liang Chen, Jinliang Liu, Jiwen Song, Linyue Liu, Shaohua Yang (2016). Calibration of a compact magnetic proton recoil neutron spectrometer. Nuclear Instruments and Methods in Physics Research Section A Accelerators Spectrometers Detectors and Associated Equipment.DOI
920. Wenxi Tian, Kun Zhang, Yu Hou, Y.P. Zhang, Suizheng Qiu, G.H. Su (2016). Hydrodynamics of two-phase flow in a rod bundle under cross-flow condition. Annals of Nuclear Energy.DOI
921. Tenglong Cong, Rui Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2016). Development and preliminary validation of a steam generator 3D thermohydraulics analysis code STAF. Nuclear Engineering and Design.DOI
922. Xiaoli Wu, Yapei Zhang, Tian Wenxi, G.H. Su, Qiu Suizheng, Wang Yang, Tong Liu, Ren Qisen, Heng Jian Huang (2016). Safety analysis of accident-tolerant fuel during LBLOCA.DOI
923. 陈森，刘余，田茂林，田文喜，秋穗正，苏光辉（2015）. 基于多孔介质模型的压水堆堆芯温场数值模拟. 《核技术》.
924. 章静，乔红威，李朋洲，巫英伟，田文喜，秋穗正，苏光辉（2015）. 管道贯穿裂纹泄漏率预测. 《原子能科学技术》.
925. 武小莉，张亚培，田文喜，苏光辉，秋穗正（2015）. 压水堆乏燃料水池泄露引发失水事故研究. 《“从设计上实际消除核电厂大量放射性物质释放”研讨会》.
926. 岳倪娜，马在勇，蔡容，苏光辉，秋穗正（2015）. 钠冷快堆事故不确定性分析. 《第十四届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室2015年度学术年会论文集》.
927. 张蕊，陈荣华，田文喜，苏光辉，秋穗正（2015）. 基于TEXAS-Ⅴ的AP1000堆外蒸汽爆炸分析. 《原子能科学技术》.
928. 章静，丛腾龙，苏光辉，秋穗正（2015）. 遗传神经网络对水平通道流动沸腾传热系数的预测. 《原子能科学技术》.
929. 仇子铖，秋穗正，巫英伟，苏光辉，田文喜，高新力（2015）. 环形通道内液态金属钠流动换热特性实验研究. 《原子能科学技术》.
930. 王章立，苏光辉，秋穗正，田文喜（2015）. 矩阵分裂算法在两相流方程求解中的应用初步研究. 《原子能科学技术》.
931. 孙都成，田文喜，秋穗正，苏光辉，张鹏，刘建昌，马盈盈（2015）. AP1000 ADS-4阀门夹带卸压实验模化分析. 《原子能科学技术》.
932. 向延，孙都成，章静，刘建昌，巫英伟，张鹏，秋穗正（2015）. 双端进气T型管夹带试验研究. 《原子能科学技术》.
933. 章静，田文喜，朱大欢，秋穗正，苏光辉（2015）. 超临界流体的泄压过程研究. 《原子能科学技术》.
934. 张蕊，干富军，左巧林，田文喜，苏光辉，秋穗正（2015）. 压水堆燃料棒束通道内过冷沸腾分析. 《原子能科学技术》.
935. 程杰，巫英伟，田文喜，秋穗正，苏光辉（2015）. 超临界水冷固态实验包层中子学与热工水力特性研究. 《原子能科学技术》.
936. 张文文，陈静，王成龙，马在勇，田文喜，秋穗正，苏光辉（2015）. 热管改进型热离子反应堆瞬态分析程序开发. 《原子能科学技术》.
937. 向延，孙都成，章静，巫英伟，张鹏，秋穗正，苏光辉（2015）. AP1000 ADS-4空气-水夹带试验研究. 《原子能科学技术》.
938. 张蕊，田文喜，丛腾龙，苏光辉，秋穗正（2015）. 湍流模型对过冷沸腾计算影响分析. 《原子能科学技术》.
939. 张大林，郑美银，田文喜，秋穗正，苏光辉（2015）. 径向步进倒料行波堆的数值研究. 《原子能科学技术》.
940. 马盈盈，钱立波，田文喜，苏光辉，秋穗正，黄彦平，闫晓（2015）. 耦合运动对流动不稳定边界的影响研究. 《核动力工程》.
941. 向延，孙都成，刘建昌，巫英伟，张鹏，秋穗正，苏光辉（2015）. AP1000中ADS-4第4级自动降压系统夹带试验研究. 《核动力工程》.
942. 王伟伟，刘丽芳，孟兆明，傅孝良，田文喜，杨燕华，苏光辉，秋穗正（2015）. AP1000小破口失水事故ADS-4液滴夹带关系式评价分析. 《核动力工程》.
943. 张蕊，田文喜，陈荣华，苏光辉，秋穗正（2015）. 熔融物碎裂特性的MPS研究. 《核动力工程》.
944. 刘利民，张大林，郑美银，秋穗正，苏光辉，田文喜（2015）. 固态钍基熔盐堆堆芯物理参数计算. 《原子能科学技术》.
945. 任五岳，边嘉伟，于国军，田文喜，张大林，苏光辉，秋穗正（2015）. 堆芯紧急冷却安注热混合实验研究. 《核动力工程》.
946. 郑美银，田文喜，初晓，张大林，苏光辉，秋穗正（2015）. 径向倒料行波堆MA嬗变可行性分析. 《原子能科学技术》.
947. 张文文，丛腾龙，田文喜，秋穗正，苏光辉，谢永诚，蒋兴（2015）. 非能动余热排出换热器换热能力数值分析. 《原子能科学技术》.
948. Sufen Li, Suizheng Qiu, Quanhu Zhang, Yonggang Huo, Hongtao Lin (2015). Fast-neutron multiplicity analysis based on liquid scintillation. Applied Radiation and Isotopes.DOI
949. Jianfu Zhang, Xiaoping Ouyang, Suizheng Qiu, Guoguang Zhang, Jinlu Ruan, Xiaodong Zhang, Xianpeng Zhang, Shaohua Yang, Jiwen Song, Linyue Liu, Hongyun Li (2015). Development of a compact magnetic proton recoil spectrometer for measurement of deuterium-tritium neutrons. Review of Scientific Instruments.DOI
950. Y.P. Zhang, Luteng Zhang, Yukun Zhou, Wenxi Tian, Suizheng Qiu, G.H. Su, Bo Zhao, Yidan Yuan, Rui Ma (2015). The COPRA experiments on the in-vessel melt pool behavior in the RPV lower head. Annals of Nuclear Energy.DOI
951. Wenwen Zhang, Zaiyong Ma, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2015). Transient thermal–hydraulic analysis of a space thermionic reactor. Annals of Nuclear Energy.DOI
952. Luteng Zhang, Yapei Zhang, Bo Zhao, Weimin Ma, Yukun Zhou, G.H. Su, Wenxi Tian, Suizheng Qiu (2015). COPRA: A large scale experiment on natural convection heat transfer in corium pools with internal heating. Progress in Nuclear Energy.DOI
953. Y.P. Zhang, Luteng Zhang, Yukun Zhou, Wenxi Tian, Suizheng Qiu, G.H. Su, Bo Zhao, Y.D. Yuan, Rui Ma (2015). Natural convection heat transfer test for in-vessel retention at prototypic Rayleigh numbers – Results of COPRA experiments. Progress in Nuclear Energy.DOI
954. Limin Liu, Dalin Zhang, Qing Lu, Kunpeng Wang, Suizheng Qiu (2015). Preliminary neutronic and thermal-hydraulic analysis of a 2 MW Thorium-based Molten Salt Reactor with Solid Fuel. Progress in Nuclear Energy.DOI
955. Nina Yue, Zaiyong Ma, Rong Cai, Hu Benxue, G.H. Su, Suizheng Qiu (2015). Thermal-hydraulic analysis of EBR-II Shutdown Heat Removal Tests SHRT-17 and SHRT-45R. Progress in Nuclear Energy.DOI
956. Bo Lin, Suizheng Qiu, G.H. Su, Wenxi Tian, Y.P. Zhang (2015). Development and verification of molten corium–concrete interaction code. Progress in Nuclear Energy.DOI
957. Luteng Zhang, Yapei Zhang, Yukun Zhou, G.H. Su, Wenxi Tian, Suizheng Qiu (2015). COPRA experiments on natural convection heat transfer in a volumetrically heated slice pool with high Rayleigh numbers. Annals of Nuclear Energy.DOI
958. Mengmeng Xi, Yingwei Wu, Wenxi Tian, G.H. Su, Suizheng Qiu (2015). The influence of ocean conditions on thermal-hydraulic characteristics of a passive residual heat removal system. Progress in Nuclear Energy.DOI
959. Jian Ge, Dalin Zhang, Wenxi Tian, Kunpeng Wang, Suizheng Qiu, G.H. Su (2015). Steady and transient solutions of neutronics problems based on finite volume method (FVM) with a CFD code. Progress in Nuclear Energy.DOI
960. Tenglong Cong, Rui Zhang, Wenxi Tian, G.H. Su, Suizheng Qiu (2015). Analysis of Westinghouse MB2 test using the Steam-generator Thermohydraulics Analysis code STAF. Annals of Nuclear Energy.DOI
961. Mengmeng Xi, Dalin Zhang, Mao Tang, Chenglong Wang, Meiyin Zheng, Suizheng Qiu (2015). Thermal hydraulic investigations and optimization on the EVC system of a PWR by CFD simulation. Nuclear Engineering and Design.DOI
962. Yu-Dang Zhang, Shasha Niu, Luteng Zhang, Suizheng Qiu, G.H. Su, Wenxi Tian (2015). A Review on Analysis of LWR Severe Accident. Journal of Nuclear Engineering and Radiation Science.DOI
963. Liang Bo Hu, Yapei Zhang, Longze Li, G.H. Su, Wenxi Tian, Suizheng Qiu (2015). Investigation of severe accident scenario of PWR response to LOCA along with SBO. Progress in Nuclear Energy.DOI
964. Meiyin Zheng, Wenxi Tian, Dalin Zhang, Suizheng Qiu, G.H. Su (2015). Minor actinide transmutation in a board type sodium cooled breed and burn reactor core. Annals of Nuclear Energy.DOI
965. Xiaoli Wu, Wei Li, Yang Wang, Yapei Zhang, Wenxi Tian, G.H. Su, Suizheng Qiu, Tong Liu, Yongjun Deng, Heng Jian Huang (2015). Preliminary safety analysis of the PWR with accident-tolerant fuels during severe accident conditions. Annals of Nuclear Energy.DOI
966. Rui Zhang, Tenglong Cong, Wenxi Tian, Suizheng Qiu, G.H. Su (2015). Effects of turbulence models on forced convection subcooled boiling in vertical pipe. Annals of Nuclear Energy.DOI
967. Rui Zhang, Tenglong Cong, Wenxi Tian, Suizheng Qiu, G.H. Su (2015). CFD analysis on subcooled boiling phenomena in PWR coolant channel. Progress in Nuclear Energy.DOI
968. Tenglong Cong, Rui Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2015). Effects of power level on thermal-hydraulic characteristics of steam generator. Progress in Nuclear Energy.DOI
969. Jie Cheng, Yingwei Wu, Wenxi Tian, G.H. Su, Suizheng Qiu (2015). Neutronics and thermo-hydraulic design of supercritical-water cooled solid breeder TBM. Fusion Engineering and Design.DOI
970. Dalin Zhang, A. Rineiski, Chenglong Wang, Zhangpeng Guo, Yao Xiao, Suizheng Qiu (2015). Development of a kinetic model for safety studies of liquid-fuel reactors. Progress in Nuclear Energy.DOI
971. Rui Zhang, Rong Hua Chen, Wen Tian, Guang Hui Su, Suizheng Qiu (2015). Analysis of AP1000 ex-vessel steam explosion behavior using TEXAS-V code. Energy science and technology.DOI
972. Tenglong Cong, Rui Zhang, Wenxi Tian, G.H. Su, Suizheng Qiu (2015). ICONE23-1345 DEVELOPMENT AND VALIDATION OF STAF : A STEAM GENERATOR 3D THERMOHYDRAULICS ANALYSIS CODE BASED ON FLUENT. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
973. Mengmeng Xi, Yingwei Wu, Wenxi Tian, G.H. Su, Suizheng Qiu (2015). ICONE23-1570 THE FLOW AND HEAT TRANSFER CHARACTERISTICS OF A PASSIVE RESIDUAL HEAT REMOVAL SYSTEM UNDER OCEAN CONDITIONS. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
974. Yongzheng Chen, Wenxi Tian, Yapei Zhang, Suizheng Qiu, G.H. Su, Ronghua Chen (2015). ICONE23-1537 EFFECTIVENESS ANALYSIS OF SEVERE ACCIDENT MANAGEMENT STRATEGIES IN LOCA SCENARIOS FOR AP1000. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
975. Xiaoli Wu, Yapei Zhang, Wenxi Tian, G.H. Su, Suizheng Qiu (2015). ICONE23-2163 SEVERE ACCIDENT ANALYSIS OF A PWR SPENT FUEL POOL IN CASE OF LOSS OF POOL COOLANT. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
976. Xiaoli Wu, Yapei Zhang, Wenxi Tian, G.H. Su, Suizheng Qiu (2015). ICONE23-1836 PRELIMINARY STUDY ON THE EFFECT OF ACCIDENT TOLERANT FUELS ON PWR SEVERE SBO. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
977. Wenwen Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su, Dalin Zhang (2015). ICONE23-1792 DEVELOPMENT OF TRANSIENT THERMAL-HYDRAULIC ANALYSIS CODE FOR THE SPACE THERMIONIC REACTOR. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
978. Kai Wang, Wuyue Ren, Suizheng Qiu, Wenxi Tian, G.H. Su, Junmei Wu (2015). ICONE23-1996 CFD SIMULATIONS OF THERMAL MIXING AT ECC SAFETY INJECTION FOR SINGLE PHASE AND AIR-WATER BUBBLY PHASE FLOW. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
979. Zicheng Qiu, Qiu Suizheng, Wu Yingwei, G.H. Su, Wenxi Tian, Xinli Gao (2015). Experimental research on heat transfer characteristic of liquid sodium flowing in annulus. Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms.
980. 丛腾龙，田文喜，秋穗正，苏光辉，谢永诚，姚彦贵（2014）. 压水堆蒸汽发生器一、二次侧稳态流场耦合分析. 《原子能科学技术》.
981. 鲁晓东，周铃岚，巫英伟，苏光辉，秋穗正，张虹（2014）. 轴向非均匀加热对并联通道流动不稳定性的影响. 《原子能科学技术》.
982. 王成龙，丛腾龙，王泽勇，田文喜，秋穗正，苏光辉，安洪振（2014）. 蒸汽发生器传热管一、二次侧耦合换热及管外过冷沸腾数值研究. 《原子能科学技术》.
983. 马在勇，仇子铖，巫英伟，田文喜，苏光辉，秋穗正（2014）. 液膜蒸干模型在液态金属CHF预测中的应用. 《原子能科学技术》.
984. 丛腾龙，田文喜，秋穗正，苏光辉（2014）. 耦合一、二次侧换热的蒸汽发生器二次侧流场分析. 《原子能科学技术》.
985. 丛腾龙，田文喜，秋穗正，苏光辉，谢永诚，姚彦贵（2014）. 蒸汽发生器二次侧三维两相流场稳态计算. 《核动力工程》.
986. 钱立波，丁书华，秋穗正（2014）. 并联矩形通道流动不稳定性模型研究. 《核动力工程》.
987. 王成龙，田文喜，苏光辉，张大林，巫英伟，秋穗正（2014）. 熔盐堆新型非能动余热排出系统中高温热管的数值分析. 《核动力工程》.
988. 李龙泽，王明军，田文喜，苏光辉，秋穗正（2014）. CPR1000全厂断电叠加蒸汽发生器安全阀误开启事故引起的严重事故分析. 《原子能科学技术》.
989. 武小莉，刘博，张亚培，田文喜，苏光辉，秋穗正（2014）. 碎片床冷却分析程序开发. 《核动力工程》.
990. 周建军，张大林，秋穗正，苏光辉，田文喜，巫英伟（2014）. 液体燃料熔盐堆三维稳态分析程序开发. 《原子能科学技术》.
991. 李华，陈平，秋穗正，苏光辉，田文喜，李云，粟敏（2014）. 多孔介质通道内两相流动特性实验研究. 《核动力工程》.
992. 王成龙，丛腾龙，田文喜，秋穗正，苏光辉（2014）. 蒸汽发生器传热管束过冷沸腾区两相流动数值模拟. 《原子能科学技术》.
993. 郑美银，田文喜，初晓，张大林，苏光辉，秋穗正，黄灏（2014）. 径向和轴向倒料行波堆概念设计研究. 《原子核物理评论》.
994. 仇子铖，秋穗正，巫英伟，苏光辉，田文喜（2014）. 环形通道内钠流动起始沸腾壁面过热度实验研究. 《原子能科学技术》.
995. 王俊，田文喜，卢佳楠，苏光辉，秋穗正（2014）. 堆内严重事故综合分析程序氧化模块MIDAC-OX的开发. 《原子能科学技术》.
996. Jianjun Zhou, Dalin Zhang, Suizheng Qiu, G.H. Su, Wenxi Tian, Yingwei Wu (2014). Three dimensional neutronic/thermal-hydraulic coupled simulation of MSR in transient state condition. Nuclear Engineering and Design.DOI
997. D.C. Sun, Y. Xiang, Wenxi Tian, J.C. Liu, P. Zhang, Suizheng Qiu, G.H. Su (2014). Experimental investigation of upper plenum entrainment in AP1000. Progress in Nuclear Energy.DOI
998. Luteng Zhang, Yukun Zhou, Yapei Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2014). Natural convection heat transfer in corium pools: A review work of experimental studies. Progress in Nuclear Energy.DOI
999. Xiaoli Wu, Wei Li, Yapei Zhang, Wenxi Tian, G.H. Su, Suizheng Qiu (2014). Analysis of accidental loss of pool coolant due to leakage in a PWR SFP. Annals of Nuclear Energy.DOI
1000. D.C. Sun, Suizheng Qiu, Y. Xiang, J. Zhang, Wenxi Tian, P. Zhang, G.H. Su (2014). Experimental investigation of liquid entrainment in ADS-4 depressurization line with steam–water. Experimental Thermal and Fluid Science.DOI
1001. Yao Xiao, Lin-Wen Hu, Suizheng Qiu, Dalin Zhang, Su Guanghui, Wenxi Tian (2014). Development of a Thermal-Hydraulic Analysis Code and Transient Analysis for a Fluoride-Salt-Cooled High-Temperature Test Reactor. Journal of Nuclear Engineering and Radiation Science.DOI
1002. D.C. Sun, J. Zhang, Y. Xiang, Wenxi Tian, J.C. Liu, P. Zhang, Suizheng Qiu (2014). Experimental investigation of liquid entrainment in vertical up tee branch with double-end gas inlets. Annals of Nuclear Energy.DOI
1003. Rui Zhang, Tenglong Cong, Wenxi Tian, Suizheng Qiu, G.H. Su (2014). Prediction of CHF in vertical heated tubes based on CFD methodology. Progress in Nuclear Energy.DOI
1004. Zitong Qiu, Zaiyong Ma, Suizheng Qiu, G.H. Su, Dalin Zhang, Yingwei Wu, Wenxi Tian (2014). Experimental research on the thermal hydraulic characteristics of sodium boiling in an annulus. Experimental Thermal and Fluid Science.DOI
1005. Zaiyong Ma, Nina Yue, Meiyin Zheng, Hu Benxue, G.H. Su, Suizheng Qiu (2014). Basic verification of THACS for sodium-cooled fast reactor system analysis. Annals of Nuclear Energy.DOI
1006. Zicheng Qiu, Zaiyong Ma, Yingwei Wu, Suizheng Qiu, G.H. Su (2014). Experimental research on the thermal hydraulic characteristics of liquid sodium flowing in annuli with low Peclet number. Annals of Nuclear Energy.DOI
1007. Meiyin Zheng, Wenxi Tian, Chu Xiao, Dalin Zhang, Suizheng Qiu, G.H. Su (2014). Preliminary design study of a board type radial fuel shuffling sodium cooled breed and burn reactor core. Nuclear Engineering and Design.DOI
1008. Yao Xiao, Lin-Wen Hu, Charles W. Forsberg, Suizheng Qiu, G.H. Su, Kun Chen, Na-Xiu Wang (2014). Analysis of the Limiting Safety System Settings of a Fluoride Salt–Cooled High-Temperature Test Reactor. Nuclear Technology.DOI
1009. Chenglong Wang, Yao Xiao, Jianjun Zhou, Dalin Zhang, Suizheng Qiu, G.H. Su, X. Z. Cai, Na-Xiu Wang, Wei Guo (2014). Computational Fluid Dynamics Analysis of a Fluoride Salt–Cooled Pebble-Bed Test Reactor. Nuclear Science and Engineering.DOI
1010. Wei Li, Xiaoli Wu, Dalin Zhang, Guanghui Su, Wenxi Tian, Suizheng Qiu (2014). Preliminary study of coupling CFD code FLUENT and system code RELAP5. Annals of Nuclear Energy.DOI
1011. Longze Li, Yapei Zhang, Wenxi Tian, G.H. Su, Suizheng Qiu (2014). MAAP5 simulation of the PWR severe accident induced by pressurizer safety valve stuck-open accident. Progress in Nuclear Energy.DOI
1012. Yao Xiao, Lin-Wen Hu, Suizheng Qiu, Dalin Zhang, G.H. Su, Wenxi Tian (2014). Development of a Thermal-Hydraulic Analysis Code and Transient Analysis for a FHTR.DOI
1013. Dalin Zhang, Zhi-Gang Zhai, A. Rineiski, Zhangpeng Guo, Chenglong Wang, Yao Xiao, Suizheng Qiu (2014). COUPLE, A Time-Dependent Coupled Neutronics and Thermal-Hydraulics Code, and its Application to MSFR.DOI
1014. Shasha Yin, Liang Gao, Wenxi Tian, Yapei Zhang, Suizheng Qiu, G.H. Su (2014). Loss-of-Flow-Accidents (LOFA) Study for 100 MW IPWR.DOI
1015. Maolin Tian, Wenxi Tian, G.H. Su, Suizheng Qiu (2014). 3D Flow Field Analysis for a Traditional II+ PWR Containment Under Normal Condition.DOI
1016. Yonghong Tian, Wenxi Tian, Zhaoming Meng, Yingwei Wu, G.H. Su, Suizheng Qiu (2014). Sub-Channel Analysis of Pb-Bi-Cooled Reactor With Modified COBRA-EN.DOI
1017. Tao Huang, Wenxi Tian, Yapei Zhang, Suizheng Qiu, G.H. Su (2014). Analysis of the Particulate Debris Bed Quenching During Top and Bottom Flood.DOI
1018. Zaiyong Ma, Yue Nina, Suizheng Qiu, Wenxi Tian, G.H. Su (2014). Application of Film Dryout Model in Liquid Metal CHF Prediction.DOI
1019. Yonghong Tian, Wenxi Tian, Dalin Zhang, G.H. Su, Suizheng Qiu (2014). Safety Analyses for Pb-Bi-Cooled Direct Contact Boiling Water Fast Reactor (PBWFR).DOI
1020. Ducheng Sun, Jianchang Liu, Wenxi Tian, Suizheng Qiu, G.H. Su, Peng Zhang, Yingying Ma (2014). Experimental Investigation of Liquid Entrainment in ADS-4 Branch Line.DOI
1021. Wenwen Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2014). Numerical Investigation on Heat Removal Capacity of Passive Residual Heat Removal Heat Exchanger.DOI
1022. Chenglong Wang, Dalin Zhang, Suizheng Qiu, Wenxi Tian, G.H. Su (2014). CFD Analysis of Subcooled Wall Boiling at Shell Side of Steam Generator With TSP.DOI
1023. Jing Zhang, Yingwei Wu, Lei Ding, Hongwei Qiao, Pengzhou Li, G.H. Su, Suizheng Qiu, Wenxi Tian (2014). A Prediction of the Leakage Through Cracks for Leak Before Break.DOI
1024. Jianchang Liu, Yue Nina, Xu Liang Xie, Sun Ducheng, Wenxi Tian, G.H. Su, Suizheng Qiu (2014). Transient Analysis of CP300 Based on RELAP5/MOD3.4.DOI
1025. Shipeng Niu, Yapei Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2014). The Code Development for the Thermo-Hydrodynamic Characteristics Study of Reflood Phase.DOI
1026. Tenglong Cong, G.H. Su, Wenxi Tian, Suizheng Qiu (2014). Development and Application of a UTSG Thermal-Hydraulic Analysis Code.DOI
1027. Yue Nina, Zaiyong Ma, Hu Benxue, Suizheng Qiu, G.H. Su (2014). Validation of THACS for Sodium Cooled Fast Reactor Based on Benchmark Analysis of EBR-II.DOI
1028. Bo Lin, Suizheng Qiu, G.H. Su, Wenxi Tian, Yapei Zhang (2014). Simulation of Molten Corium Concrete Interaction With the MOCO Code.DOI
1029. Jun Wang, Michael L. Corradini, Wen Fu, Troy Haskin, Wenxi Tian, Yapei Zhang, G.H. Su, Suizheng Qiu (2014). Comparison of CORA and MELCOR Core Degradation Simulation and MELCOR Oxidation Model.DOI
1030. Xiaoli Wu, Yapei Zhang, Wenxi Tian, Guanghui Su, Suizheng Qiu (2014). Analysis of a Loss of Heat Removal Accident in a PWR Spent Fuel Pool.DOI
1031. Zicheng Qiu, Zaiyong Ma, Suizheng Qiu, Yingwei Wu, G.H. Su (2014). Experimental Study on the Thermal Hydraulic Characteristics of Liquid Sodium Flowing in an Annulus.DOI
1032. Chenglong Wang, Yao Xiao, Jianjun Zhou, Dalin Zhang, Suizheng Qiu, Wenxi Tian, G.H. Su (2014). Thermal Hydraulic Studies of a Fluoride Salt Cooled High Temperature Test Reactor With Different CFD Methods.DOI
1033. Wei Li, Xiaoli Wu, Yapei Zhang, Deyou Ma, Yongzheng Chen, Wenxi Tian, Suizheng Qiu, G.H. Su (2014). Analysis of PWR RPV lower head SBLOCA scenarios with the failure of high-pressure injection system using MAAP5. Progress in Nuclear Energy.DOI
1034. Xiaoli Wu, Wei Li, Yapei Zhang, Wenxi Tian, G.H. Su, Suizheng Qiu (2014). Analysis of the loss of pool cooling accident in a PWR spent fuel pool with MAAP5. Annals of Nuclear Energy.DOI
1035. Jun Wang, Wenxi Tian, Yapei Zhang, Lie Chen, Longze Li, Luteng Zhang, Yukun Zhou, G.H. Su, Suizheng Qiu (2014). The development of Module In-vessel degraded severe accident Analysis Code MIDAC and the relevant research for CPR1000 during the station blackout scenario. Progress in Nuclear Energy.DOI
1036. D.C. Sun, Y. Xiang, J. Zhang, Wenxi Tian, P. Zhang, Suizheng Qiu, G.H. Su (2014). Experimental investigation of liquid entrainment in AP1000 ADS-4 branch line with air–water. Experimental Thermal and Fluid Science.DOI
1037. Zaiyong Ma, Zicheng Qiu, Yingwei Wu, Suizheng Qiu, G.H. Su, Wenxi Tian (2014). Analysis of heat flux and velocity effects on nucleation superheat in liquid metals based on dynamic effects. Annals of Nuclear Energy.DOI
1038. Zhen-Hui Liang, Hang Zhang, Suizheng Qiu, G.H. Su (2014). Experimental investigation on thermal-hydraulic characteristics of narrow rectangular channels with simulated neutronic feedback. Nuclear Engineering and Design.DOI
1039. Y.P. Zhang, G.H. Su, Suizheng Qiu, Wenxi Tian, X. Gaus-Liu, Frank Kretzschmar, A. Miassoedov (2014). Numerical study on the heat transfer characteristics of LIVE-L4 melt pool with a partial solidification process. Progress in Nuclear Energy.DOI
1040. Dalin Zhang, Meiyin Zheng, HongZhen An, XueNong Chen, Wenxi Tian, Suizheng Qiu, G.H. Su (2014). Numerical studies of stepwise radial fuel shuffling in a traveling wave reactor. Science China Technological Sciences.DOI
1041. Mingjun Wang, Dalin Zhang, Suizheng Qiu, Wenxi Tian, G.H. Su (2014). Accident analyses for china pressurizer reactor with an innovative conceptual design of passive residual heat removal system. Nuclear Engineering and Design.DOI
1042. D.C. Sun, Wenxi Tian, Suizheng Qiu, G.H. Su, P. Zhang, J.C. Liu, Yingchao Ma (2014). Scaling analysis of AP1000 ADS-4 entrainment and depressurization. Progress in Nuclear Energy.DOI
1043. Jun Wang, Wenxi Tian, Yuqiao Fan, Keyou Mao, Jianan Lu, G.H. Su, Suizheng Qiu (2014). The development of a zirconium oxidation calculating program module for Module In-vessel Degraded Analysis Code MIDAC. Progress in Nuclear Energy.DOI
1044. Zhaoming Meng, Laishun Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2014). Corrigendum to “Entrainment at T-junction: A review work” [Prog. Nucl. Energy 70 (January 2014) 221–241]. Progress in Nuclear Energy.DOI
1045. Jing Zhang, Dahuan Zhu, Wenxi Tian, Suizheng Qiu, G.H. Su, Dalin Zhang (2014). Depressurization study of supercritical fluid blowdown from simple vessel. Annals of Nuclear Energy.DOI
1046. Meiyin Zheng, Wenxi Tian, Chu Xiao, Dalin Zhang, Yingwei Wu, Suizheng Qiu, G.H. Su (2014). Study of traveling wave reactor (TWR) and CANDLE strategy: A review work. Progress in Nuclear Energy.DOI
1047. Meiyin Zheng, Tian Wenxi, Chu Xiao, Dalin Zhang, G.H. Su, Qiu Suizheng, Hao Huang (2014). Design of radial and axial fuel shuffling TWR. Yuanzihe wuli pinglun.
1048. Zicheng Qiu, Qiu Suizheng, Wu Yingwei, Su Guangwei, Wenxi Tian (2014). Experimental study on incipient boiling wall superheat of sodium flowing in annulus. Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms.
1049. 韦宏洋，丛腾龙，田文喜，杨江，秋穗正，苏光辉（2013）. 钠冷行波堆TP-1瞬态安全分析. 《原子能科学技术》.
1050. 陈静，田文喜，韦宏洋，巫英伟，秋穗正，苏光辉（2013）. 基于多孔介质模型的行波堆TP-1堆芯稳态温度场与流场数值模拟. 《原子能科学技术》.
1051. 王成龙，田文喜，苏光辉，张大林，巫英伟，秋穗正（2013）. 新概念熔盐堆非能动余热排出系统中钠热管的特性研究. 《原子能科学技术》.
1052. 韦宏洋，田文喜，丛腾龙，黄灏，苏光辉，秋穗正（2013）. 行波堆TP-1堆芯热工水力单通道与子通道分析方法研究. 《原子能科学技术》.
1053. 王美，巫英伟，田文喜，苏光辉，秋穗正（2013）. 液态金属钠在圆管中湍流传热特性研究. 《原子能科学技术》.
1054. 郭张鹏，张大林，肖瑶，秋穗正，田文喜，苏光辉（2013）. 物理-热工耦合计算方法在熔盐堆稳态分析中的应用. 《原子能科学技术》.
1055. 李伟，田文喜，秋穗正，苏光辉（2013）. 基于RELAP5的双功能液态锂铅实验包层模块安全分析. 《原子能科学技术》.
1056. 肖瑶，巫英伟，苏光辉，秋穗正（2013）. 压水堆核电厂一回路仿真可视化研究. 《原子能科学技术》.
1057. 左娟莉，田文喜，秋穗正，苏光辉（2013）. 铅铋合金冷却反应堆内气泡提升泵提升自然循环能力的理论研究. 《原子能科学技术》.
1058. 王明军，苏亚丽，秋穗正，苏光辉，田文喜（2013）. LBB泄漏率计算与热力学非平衡效应影响评估. 《原子能科学技术》.
1059. 王俊，田文喜，田永红，苏光辉，秋穗正（2013）. 铅铋冷却快堆子通道热工水力初步数值分析. 《原子能科学技术》.
1060. 张亚培，田文喜，秋穗正，苏光辉（2013）. 基于SIMPLE方法的熔融物凝固模型研究. 《核动力工程》.
1061. 田晓艳，田文喜，朱大欢，秋穗正，苏光辉，夏榜样（2013）. 基于频域法超临界水冷堆CSR1000流动不稳定性研究. 《原子能科学技术》.
1062. 王杰，苏光辉，田文喜，秋穗正，向斌，张国书，冯开明（2013）. 基于RELAP5的中国氦冷固态包层真空室外破口瞬态特性分析. 《原子能科学技术》.
1063. 田文喜，田晓艳，冯健，秋穗正，苏光辉，鲁剑超（2013）. 超临界水冷堆CSR1000流动不稳定性研究. 《核动力工程》.
1064. 王美，巫英伟，田文喜，苏光辉，秋穗正（2013）. 液态金属钠在环管中湍流传热特性研究. 《核动力工程》.
1065. 朱大欢，田文喜，秋穗正，苏光辉（2013）. 基于TACOS程序的SCWR典型事故瞬态特性研究. 《核动力工程》.
1066. 李昕，田文喜，陈荣华，王来顺，苏光辉，秋穗正（2013）. 基于MPS方法模拟液态铅铋合金中弹状气泡上升. 《原子能科学技术》.
1067. 封坤，田文喜，巫英伟，苏光辉，秋穗正，余红星（2013）. 熔融物与下封头间球形窄缝通道内CHF理论研究. 《原子能科学技术》.
1068. 朱大欢，苏亚丽，赵皓，田文喜，苏光辉，秋穗正（2013）. 超临界水堆的瞬态分析程序开发. 《原子能科学技术》.
1069. 杨江，田文喜，苏光辉，秋穗正（2013）. AP1000小破口事故下非能动氮气安注箱的瞬态特性研究. 《原子能科学技术》.
1070. Jianjun Zhou, Chenglong Wang, HongZhen An, Dalin Zhang, Suizheng Qiu, G.H. Su, Wenxi Tian, Yingwei Wu (2013). Three dimensional neutronic/thermal-hydraulic coupled simulation of MSR in steady state condition. Nuclear Engineering and Design.DOI
1071. Hao Feng Zhao, Dahuan Zhu, Khurrum Saleem Chaudri, Suizheng Qiu, Wenxi Tian, G.H. Su (2013). Preliminary transient thermal-hydraulic analysis for new coated UN and UC fuel options in SCWR. Progress in Nuclear Energy.DOI
1072. Zaiyong Ma, Zicheng Qiu, Yingwei Wu, Suizheng Qiu, Guanghui Su (2013). An analysis of incipient boiling superheat in alkali liquid metals. International Journal of Heat and Mass Transfer.DOI
1073. Longze Li, Mingjun Wang, Wenxi Tian, G.H. Su, Suizheng Qiu (2013). Severe accident analysis for a typical PWR using the MELCOR code. Progress in Nuclear Energy.DOI
1074. Libo Qian, Shuhua Ding, Suizheng Qiu (2013). Research on two-phase flow instability in parallel rectangular channels. Annals of Nuclear Energy.DOI
1075. Jun Wang, Wenxi Tian, Keliang Feng, H.X. Yu, Y.P. Zhang, G.H. Su, Suizheng Qiu (2013). Development of CHF models for inner and outer RPV gaps in a meltdown severe accident. Nuclear Engineering and Design.DOI
1076. Xin Li, Wen Tian, Rong Hua Chen, Lai Shun Wang, Guang Hui Su, Suizheng Qiu (2013). Numerical simulation of Taylor bubble rising in liquid lead-bismuth eutectic based on MPS method. Energy science and technology.DOI
1077. Zhangpeng Guo, Chenglong Wang, Dalin Zhang, Khurrum Saleem Chaudri, Wenxi Tian, G.H. Su, Suizheng Qiu (2013). The effects of core zoning on optimization of design analysis of molten salt reactor. Nuclear Engineering and Design.DOI
1078. Zhaoming Meng, Laishun Wang, Wenxi Tian, Suizheng Qiu, G.H. Su (2013). Entrainment at T-junction: A review work. Progress in Nuclear Energy.DOI
1079. Xinli Gao, Tiejun Zu, Wenxi Tian, Suizheng Qiu, Guanghui Su, Hong‐Chun Wu (2013). Thermal-hydraulic design of water-cooled pressure tube blanket for a fusion driven subcritical reactor. Fusion Engineering and Design.DOI
1080. Tenglong Cong, Wenxi Tian, G.H. Su, Suizheng Qiu, Yongcheng Xie, Yao Yangui (2013). Three-dimensional study on steady thermohydraulics characteristics in secondary side of steam generator. Progress in Nuclear Energy.DOI
1081. Chenglong Wang, Dalin Zhang, Suizheng Qiu, Wenxi Tian, Yingwei Wu, G.H. Su (2013). Study on the characteristics of the sodium heat pipe in passive residual heat removal system of molten salt reactor. Nuclear Engineering and Design.DOI
1082. Chenglong Wang, Tenglong Cong, Suizheng Qiu, Wenxi Tian, Yingwei Wu, G.H. Su (2013). Numerical prediction of subcooled wall boiling in the secondary side of SG tubes coupled with primary coolant. Annals of Nuclear Energy.DOI
1083. Yali Su, Khurrum Saleem Chaudri, Wenxi Tian, G.H. Su, Suizheng Qiu (2013). Optimization study for thermal efficiency of supercritical water reactor nuclear power plant. Annals of Nuclear Energy.DOI
1084. Meiyin Zheng, Wenxi Tian, Hongyang Wei, Dalin Zhang, Yingwei Wu, Suizheng Qiu, G.H. Su (2013). Development of a MCNP–ORIGEN burn-up calculation code system and its accuracy assessment. Annals of Nuclear Energy.DOI
1085. Zhike Lan, Dahuan Zhu, Wenxi Tian, Guanghui Su, Suizheng Qiu (2013). Numerical approaches and analysis of spray characteristics for pressuriser nozzles. The Canadian Journal of Chemical Engineering.DOI
1086. Mingjun Wang, Suizheng Qiu, G.H. Su, Wenxi Tian (2013). Research on the leak-rate characteristics of leak-before-break (LBB) in pressurized water reactor (PWR). Applied Thermal Engineering.DOI
1087. Wenxi Tian, R. H. Chen, Juan Li Zuo, Suizheng Qiu, G.H. Su, Y. Ishiwatari, Y. Oka (2013). Numerical Simulation on Collapse of Vapor Bubble Using Particle Method. Heat Transfer Engineering.DOI
1088. Tenglong Cong, Wenxi Tian, Suizheng Qiu, G.H. Su (2013). Study on secondary side flow of steam generator with coupled heat transfer from primary to secondary side. Applied Thermal Engineering.DOI
1089. Zhike Lan, Dahuan Zhu, Wenxi Tian, G.H. Su, Suizheng Qiu (2013). Experimental study on spray characteristics of pressure-swirl nozzles in pressurizer. Annals of Nuclear Energy.DOI
1090. Xiaodong Lu, Yingwei Wu, Linglan Zhou, Wenxi Tian, G.H. Su, Suizheng Qiu, Zhang Hong (2013). Theoretical investigations on two-phase flow instability in parallel channels under axial non-uniform heating. Annals of Nuclear Energy.DOI
1091. Mingjun Wang, Suizheng Qiu, G.H. Su, Wenxi Tian (2013). Preliminary study of parameter uncertainty influence on Pressurized Water Reactor core design. Progress in Nuclear Energy.DOI
1092. Zhangpeng Guo, Jianjun Zhou, Dalin Zhang, Khurrum Saleem Chaudri, Wenxi Tian, G.H. Su, Suizheng Qiu (2013). Coupled neutronics/thermal-hydraulics for analysis of molten salt reactor. Nuclear Engineering and Design.DOI
1093. Yao Xiao, Lin-Wen Hu, Charles W. Forsberg, Suizheng Qiu, G.H. Su (2013). Licensing Considerations of a Fluoride Salt Cooled High Temperature Test Reactor. Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors.DOI
1094. Jun Wang, Wenxi Tian, Jianan Lu, Yingying Ma, G.H. Su, Suizheng Qiu (2013). The Research on Core Melting Process: Oxidation. Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes.DOI
1095. Yingying Ma, Wenxi Tian, G.H. Su, Libo Qian, Youjia Zhang, Yanping Huang, Yanlin Wang, Suizheng Qiu (2013). Theoretical Research on Flow Instability in Parallel Channels Under Motion Conditions.DOI
1096. Chenglong Wang, Suizheng Qiu, Wenxi Tian, Yingwei Wu, G.H. Su (2013). Transient Study on Sodium Heat Pipe in Passive Heat Removal System of Molten Salt Reactor.DOI
1097. Longze Li, Mingjun Wang, Wenxi Tian, G.H. Su, Suizheng Qiu (2013). The Severe Accident Analysis of CPR1000 Based on MELCOR Code.DOI
1098. Tenglong Cong, Wenxi Tian, G.H. Su, Suizheng Qiu (2013). Three-Dimensional Steady Simulation on Two-Phase Flow in Secondary Side of Steam Generator.DOI
1099. Jie Wang, G.H. Su, Wenxi Tian, Suizheng Qiu (2013). Development of a Thermal-Hydraulic Code for Chinese Helium-Cooled Ceramic Breeder TBM Cooling System. Volume 5: Fuel Cycle, Radioactive Waste Management and Decommissioning; Reactor Physics and Transport Theory; Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls; Fusion Engineering.DOI
1100. Xiaodong Lu, Linglan Zhou, Zhang Hong, Yingwei Wu, G.H. Su, Suizheng Qiu (2013). The Influence of Non-Uniform Heating on Two-Phase Flow Instability in Parallel Channels.DOI
1101. Tenglong Cong, Hongyang Wei, Wenxi Tian, G.H. Su, Suizheng Qiu (2013). Transient and Safety Analysis Code for TP-1 Sodium Cooled TWR.DOI
1102. Jianjun Zhou, Suizheng Qiu, Zhangpeng Guo, G.H. Su (2013). The Optimization Design of Lower Plenum and Distribution Plates in MSR. Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors.DOI
1103. Jie Wang, Wenxi Tian, G.H. Su, Suizheng Qiu (2013). Development of TSACO and application to Chinese HCCB TBM cooling system. Fusion Engineering and Design.DOI
1104. Y.H. Tian, G.H. Su, Jun Wang, Wenxi Tian, Suizheng Qiu (2013). Code development and safety analyses for Pb–Bi-cooled direct contact boiling water fast reactor (PBWFR). Progress in Nuclear Energy.DOI
1105. Chenglong Wang, Zhangpeng Guo, Dalin Zhang, Suizheng Qiu, Wenxi Tian, Yingwei Wu, G.H. Su (2013). Transient behavior of the sodium–potassium alloy heat pipe in passive residual heat removal system of molten salt reactor. Progress in Nuclear Energy.DOI
1106. Yali Su, Jian Feng, Hao Jiang Zhao, Wenxi Tian, Guanghui Su, Suizheng Qiu (2013). Theoretical study on the flow instability of supercritical water in the parallel channels. Progress in Nuclear Energy.DOI
1107. W.W. Wang, G.H. Su, Wenxi Tian, Suizheng Qiu (2013). Research on thermal hydraulic behavior of small-break LOCAs in AP1000. Nuclear Engineering and Design.DOI
1108. Zicheng Qiu, Zaiyong Ma, Suizheng Qiu, Yingwei Wu, Wenxi Tian, G.H. Su, Dalin Zhang (2013). Experimental research on the incipient boiling wall superheat of sodium. Progress in Nuclear Energy.DOI
1109. Yingwei Wu, Xin Li, Xiaolei Yu, Suizheng Qiu, G.H. Su, Wenxi Tian (2013). Subchannel thermal-hydraulic analysis of the fuel assembly for liquid sodium cooled fast reactor. Progress in Nuclear Energy.DOI
1110. Khurrum Saleem Chaudri, Wenxi Tian, G.H. Su, Suizheng Qiu (2013). Coupled neutronics/thermal hydraulics evaluation for thorium based fuels in thermal spectrum SCWR. Progress in Nuclear Energy.DOI
1111. Y.P. Zhang, G.H. Su, Suizheng Qiu, Wenxi Tian, X. Gaus-Liu, Frank Kretzschmar, A. Miassoedov (2013). A simple novel and fast computational model for the LIVE-L4. Progress in Nuclear Energy.DOI
1112. Z.L. Wang, Wenxi Tian, G.H. Su, Suizheng Qiu, Liang Zhao, Qiaolin Zuo, Yingwei Wu, Dalin Zhang (2013). Development of a thermal hydraulic code for an integral reactor. Progress in Nuclear Energy.DOI
1113. W.W. Wang, G.H. Su, ZeYu Meng, Wenxi Tian, Suizheng Qiu (2013). Analyses of liquid entrainment through ADS-4 in AP1000 during a typical small break LOCA transient. Annals of Nuclear Energy.DOI
1114. L. Zhao, G.H. Su, Suizheng Qiu, Z.L. Wang (2013). Thermal–hydraulic performance analysis of IPWR during full pressure start-up mode. Annals of Nuclear Energy.DOI
1115. Juanli Zuo, Wenxi Tian, Ronghua Chen, Suizheng Qiu, G.H. Su (2013). Research on enhancement of natural circulation capability in lead–bismuth alloy cooled reactor by using gas-lift pump. Nuclear Engineering and Design.DOI
1116. Qiaolin Zuo, Suizheng Qiu, Wei Lu, Wenxi Tian, G.H. Su, Zejun Xiao (2013). Water hammer characteristics of integral pressurized water reactor primary loop. Nuclear Engineering and Design.DOI
1117. Yao Xiao, Yingwei Wu, Wenxi Tian, Suizheng Qiu, G.H. Su (2013). Development of VTSAS 1.0 and application to an IPWR. Nuclear Engineering and Design.DOI
1118. Wei Li, Wenxi Tian, Suizheng Qiu, G.H. Su, Hong Jiao, Yunqing Bai, Hongli Chen, Yican Wu (2013). Preliminary thermal-hydraulic and safety analysis of China DFLL-TBM system. Fusion Engineering and Design.DOI
1119. Mingchao Wang, Suizheng Qiu, Yingwei Wu, Wenxi Tian, G.H. Su (2013). Numerical research on local heat transfer distribution of liquid sodium turbulent flow in an annulus. Progress in Nuclear Energy.DOI
1120. Mingjun Wang, Suizheng Qiu, Wenxi Tian, G.H. Su, Yapei Zhang (2013). The comparison of designed water-cooled and air-cooled passive residual heat removal system for 300MW nuclear power plant during the feed-water line break scenario. Annals of Nuclear Energy.DOI
1121. Xin Li, Wenxi Tian, Ronghua Chen, G.H. Su, Suizheng Qiu (2013). Numerical simulation on single Taylor bubble rising in LBE using moving particle method. Nuclear Engineering and Design.DOI
1122. Mingjun Wang, Wenxi Tian, Suizheng Qiu, G.H. Su, Yapei Zhang (2013). An evaluation of designed passive Core Makeup Tank (CMT) for China pressurized reactor (CPR1000). Annals of Nuclear Energy.DOI
1123. Bin Hu, Yingwei Wu, Wenxi Tian, G.H. Su, Suizheng Qiu (2013). Development of a transient thermal-hydraulic code for analysis of China Demonstration Fast Reactor. Annals of Nuclear Energy.DOI
1124. Juanli Zuo, Wenxi Tian, Ronghua Chen, Suizheng Qiu, G.H. Su (2013). Two-dimensional numerical simulation of single bubble rising behavior in liquid metal using moving particle semi-implicit method. Progress in Nuclear Energy.DOI
1125. Hongchun Wu, Tiejun Zu, Suizheng Qiu, Xinli Gao, Youqi Zheng, Liangzhi Cao, Wenxi Tian (2013). A fusion–fission hybrid reactor with water-cooled pressure tube blanket for energy production. Progress in Nuclear Energy.DOI
1126. R. H. Chen, Michael L. Corradini, G.H. Su, Suizheng Qiu (2013). Development of a Solidification Model for TEXAS-VI Code and Application to FARO L14 Analysis. Nuclear Science and Engineering.DOI
1127. 左巧林，秋穗正，芦苇，苏光辉，田文喜，王盛，肖泽军（2012）. 核反应堆一回路系统水锤数值模拟. 《核动力工程》.
1128. 钱立波，田文喜，秋穗正，苏光辉，李勇，黄彦平，闫晓（2012）. 一维冷却剂通道海洋条件附加力模型研究. 《核动力工程》.
1129. 王伟伟，苏光辉，田文喜，秋穗正（2012）. AP1000自动降压系统误开启事故仿真分析. 《原子能科学技术》.
1130. 张亚培，田文喜，秋穗正，苏光辉，余红星，闫晓（2012）. 倾角变化的窄缝通道内CHF理论模型. 《核动力工程》.
1131. 冯健，田文喜，巫英伟，田晓燕，秋穗正，苏光辉（2012）. 超临界水并联通道流动不稳定性理论研究. 《原子能科学技术》.
1132. 王伟伟，苏光辉，田文喜，秋穗正（2012）. 基于多区非平衡模型的稳压器动态仿真与验证. 《原子能科学技术》.
1133. 李华，秋穗正，蔡孝玉，苏光辉，田文喜（2012）. 球床式水冷堆堆芯热工水力特性分析. 《原子能科学技术》.
1134. 王明军，张亚培，田文喜，苏光辉，秋穗正（2012）. CPR1000二次侧非能动应急热阱设计与事故缓解能力分析. 《原子能科学技术》.
1135. 杨震，苏光辉，田文喜，秋穗正（2012）. 水堆燃料元件性能分析及程序FROBA开发. 《原子能科学技术》.
1136. 王明军，张亚培，田文喜，苏光辉，秋穗正（2012）. 主给水管道破口尺寸对CPR1000二次侧非能动应急热阱事故缓解能力影响研究. 《原子能科学技术》.
1137. Qiu Suizheng (2012). Dynamic Simulation and Verification of Pressurizer Based on Nonequilibrium Multi-region Model. Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms.
1138. Qiu Suizheng (2012). Simulation Analysis of Inadvertent Opening of Automatic Depressurization System for AP1000. Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms.
1139. J. Yang, W.W. Wang, Suizheng Qiu, Wenxi Tian, G.H. Su, Yingwei Wu (2012). Simulation and analysis on 10-in. cold leg small break LOCA for AP1000. Annals of Nuclear Energy.DOI
1140. Khurrum Saleem Chaudri, Wenxi Tian, Yali Su, Hao Feng Zhao, Dahuan Zhu, G.H. Su, Suizheng Qiu (2012). Coupled analysis for new fuel design using UN and UC for SCWR. Progress in Nuclear Energy.DOI
1141. Zhangpeng Guo, Dalin Zhang, Yao Xiao, Wenxi Tian, G.H. Su, Suizheng Qiu (2012). Simulations of unprotected loss of heat sink and combination of events accidents for a molten salt reactor. Annals of Nuclear Energy.DOI
1142. Jun Wang, Wenxi Tian, Y.H. Tian, G.H. Su, Suizheng Qiu (2012). A sub-channel analysis code for advanced lead bismuth fast reactor. Progress in Nuclear Energy.DOI
1143. Jie Wang, Wenxi Tian, G.H. Su, Suizheng Qiu, Bin Xiang, Guoshu Zhang, Kaiming Feng (2012). Thermal–hydraulic and safety analysis for Chinese helium-cooled solid breeder TBM cooling system. Fusion Engineering and Design.DOI
1144. Tenglong Cong, G.H. Su, Suizheng Qiu, Wenxi Tian (2012). Applications of ANNs in flow and heat transfer problems in nuclear engineering: A review work. Progress in Nuclear Energy.DOI
1145. Dahuan Zhu, Wenxi Tian, Hao Feng Zhao, Yali Su, Suizheng Qiu, G.H. Su (2012). Comparative study of transient thermal–hydraulic characteristics of SCWRs with different core design. Annals of Nuclear Energy.DOI
1146. Hongxing Yu, Wenxi Tian, Zhen Yang, G.H. Su, Suizheng Qiu (2012). Development of Fuel ROd Behavior Analysis code (FROBA) and its application to AP1000. Annals of Nuclear Energy.DOI
1147. Wenwei Liu, Wenxi Tian, Yingwei Wu, G.H. Su, Suizheng Qiu, Xiao Yan, Yanping Huang, Dongxiao Du (2012). An improved mechanistic critical heat flux model and its application to motion conditions. Progress in Nuclear Energy.DOI
1148. Xiaoyan Tian, Wenxi Tian, Dahuan Zhu, Suizheng Qiu, G.H. Su, Bangyang Xia (2012). Flow instability analysis of supercritical water-cooled reactor CSR1000 based on frequency domain. Annals of Nuclear Energy.DOI
1149. Yali Su, Jian Feng, Wenxi Tian, Suizheng Qiu, G.H. Su (2012). Theoretical Study on the Flow Instability of Supercritical Water in the Parallel Channels. Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles.DOI
1150. Yonghong Tain, G.H. Su, jun yi Wang, Wenxi Tian, Suizheng Qiu (2012). The Thermal-Hydraulic Analyses of Transients in PBWFR.DOI
1151. Yao Xiao, Dalin Zhang, Zhangpeng Guo, Suizheng Qiu (2012). Numerical Analysis for a Molten Salt Reactor in the Presence of Fissile Lump.DOI
1152. Dahuan Zhu, Wenxi Tian, Suizheng Qiu, G.H. Su (2012). Comparison of Transient Responses for SCWRs With Different Flow Path Designs Under Loss of Flow Accident. Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles.DOI
1153. Xinli Gao, Tiejun Zu, Hongchun Wu, Suizheng Qiu, G.H. Su, Wenxi Tian (2012). Thermal-Hydraulics Design of Water-Cooled Pressure Tube Blanket for a Fusion Driven Subcritical Reactor. Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles.DOI
1154. Jie Wang, G.H. Su, Wenxi Tian, Suizheng Qiu (2012). Thermal-Hydraulic Analysis of Design Basis Accidents for Chinese Helium-Cooled Solid Breeder TBM. Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles.DOI
1155. Yingwei Wu, G.H. Su, Suizheng Qiu, Wenxi Tian (2012). Development of a thermal–hydraulic analysis software for a passive residual heat removal system. Annals of Nuclear Energy.DOI
1156. Yao Xiao, Dalin Zhang, Zhangpeng Guo, Yingwei Wu, Wenxi Tian, G.H. Su, Suizheng Qiu (2012). Numerical analysis for a molten salt reactor in the presence of localized perturbations. Progress in Nuclear Energy.DOI
1157. Zaiyong Ma, Yingwei Wu, Zicheng Qiu, Wenxi Tian, Guanghui Su, Suizheng Qiu (2012). An innovative method for prediction of liquid metal heat transfer rate for rod bundles based on annuli. Annals of Nuclear Energy.DOI
1158. Hongxing Yu, Yapei Zhang, G.H. Su, Suizheng Qiu, Wenxi Tian (2012). A theoretical CHF model for downward facing surfaces and gaps under saturated boiling. International Journal of Multiphase Flow.DOI
1159. Zhen Hui Liang, Yan Fei Wen, Chao Gao, Wen Tian, Yingwei Wu, Guang Hui Su, Suizheng Qiu (2012). Experimental investigation on flow and heat transfer characteristics of single-phase flow with simulated neutronic feedback in narrow rectangular channel. Nuclear Engineering and Design.DOI
1160. Weifeng Ni, Suizheng Qiu, G.H. Su, Wenxi Tian, Yingwei Wu (2012). Numerical investigation of buoyant effect on flow and heat transfer of Lithium–Lead Eutectic in DFLL–TBM. Progress in Nuclear Energy.DOI
1161. Mingjun Wang, Hao Feng Zhao, Yapei Zhang, G.H. Su, Wenxi Tian, Suizheng Qiu (2012). Research on the designed emergency passive residual heat removal system during the station blackout scenario for CPR1000. Annals of Nuclear Energy.DOI
1162. Khurrum Saleem Chaudri, Yali Su, Ronghua Chen, Wenxi Tian, G.H. Su, Suizheng Qiu (2012). Development of sub-channel code SACoS and its application in coupled neutronics/thermal hydraulics system for SCWR. Annals of Nuclear Energy.DOI
1163. Hua Li, Suizheng Qiu, Youjia Zhang, G.H. Su, Wenxi Tian (2012). Thermal hydraulic investigations with different fuel diameters of pebble bed water cooled reactor in CFD simulation. Annals of Nuclear Energy.DOI
1164. 马在勇，仇子铖，王美，田文喜，苏光辉，秋穗正（2011）. 液态金属棒束传热的理论分析. 《原子能科学技术》.
1165. 张亚培，田文喜，秋穗正，苏光辉（2011）. CPR1000非能动应急给水系统瞬态特性分析. 《原子能科学技术》.
1166. 陈荣华，田文喜，苏光辉，秋穗正（2011）. 流动泡核沸腾中汽泡行为的MPS数值模拟. 《原子能科学技术》.
1167. 王伟伟，苏光辉，田文喜，秋穗正（2011）. AP1000主回路系统热工水力瞬态计算程序RETAC的开发. 《原子能科学技术》.
1168. 陈荣华，田文喜，左娟莉，苏光辉，秋穗正（2011）. 基于MPS方法的汽泡冷凝与融合特性研究. 《工程热物理学报》.
1169. 杨震，苏光辉，田文喜，秋穗正（2011）. 基于微液层理论的下封头外部流体CHF理论计算. 《核动力工程》.
1170. 张亚培，田文喜，秋穗正，苏光辉（2011）. CPR1000全厂断电事故瞬态特性分析. 《原子能科学技术》.
1171. 樊普，贾斗南，秋穗正（2011）. 低压下水欠热流动沸腾的两相CFD数值模拟研究. 《原子能科学技术》.
1172. 王伟伟，苏光辉，田文喜，秋穗正（2011）. AP1000非能动余热排出系统建模与瞬态数值分析. 《原子能科学技术》.
1173. 杨江，田文喜，苏光辉，秋穗正（2011）. AP1000冷管段小破口失水事故分析. 《原子能科学技术》.
1174. 左娟莉，田文喜，秋穗正，陈荣华，苏光辉（2011）. 液态金属内单个气泡上升行为的MPS法数值模拟. 《原子能科学技术》.
1175. 焦宏，田文喜，秋穗正，苏光辉（2011）. 双冷嬗变包层第一壁热工水力特性数值模拟研究. 《原子能科学技术》.
1176. 陈荣华，田文喜，左娟莉，苏光辉，秋穗正，许建辉（2011）. 基于MPS方法的液态铅铋合金内气泡上升流数值模拟. 《核动力工程》.
1177. 张亚培，田文喜，秋穗正，苏光辉（2011）. CPR1000非能动余热排出系统流动不稳定性分析. 《核动力工程》.
1178. Wang Weiwei, Tian Wenxi, Su Guanghui, Qiu Suizheng (2011). Development of a thermal–hydraulic safety analysis code RETAC for AP1000. Progress in Nuclear Energy.DOI
1179. Weiwei Wang, G.H. Su, Tian Wenxi, Qiu Suizheng (2011). Development of Thermal-Hydraulic Transient Analysis Code RETAC for AP1000 Primary Loop. Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms.
1180. Qiu Suizheng (2011). CFD Investigation of Subcooled Flow Boiling Model Under Low Pressure. Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms.
1181. Dongxiao Du, Wenxi Tian, G.H. Su, Suizheng Qiu, Yanping Huang, Xiao Yan (2011). Theoretical study on the characteristics of critical heat flux in vertical narrow rectangular channels. Applied Thermal Engineering.DOI
1182. Rong Hua Chen, Wen Tian, Juan Li Zuo, Guang Hui Su, Suizheng Qiu (2011). Numerical investigation on bubble condensation and coalescence of bubble pairs using moving particle semi-implicit method. Journal of Engineering Thermophysics.
1183. Y.P. Zhang, Suizheng Qiu, G.H. Su, Wenxi Tian (2011). Design and transient analyses of emergency passive residual heat removal system of CPR1000. Nuclear Engineering and Design.DOI
1184. Z.L. Wang, Wenxi Tian, Yingwei Wu, Suizheng Qiu, G.H. Su (2011). Numerical study on annular tube once-through steam generator using compressible flow model. Annals of Nuclear Energy.DOI
1185. Rong Hua Chen, Wen Tian, Juan Li Zuo, Guang Hui Su, Suizheng Qiu, Jian Hui Xu (2011). Numerical analysis of bubble rising behavior in a liquid metal using MPS.
1186. Rong Hua Chen, Wen Tian, Guang Hui Su, Suizheng Qiu (2011). Numerical simulation on bubble growth and departure by MPS. Energy science and technology.
1187. Tenglong Cong, Ronghua Chen, G.H. Su, Suizheng Qiu, Wenxi Tian (2011). Analysis of CHF in saturated forced convective boiling on a heated surface with impinging jets using artificial neural network and genetic algorithm. Nuclear Engineering and Design.DOI
1188. Dahuan Zhu, Hao Feng Zhao, Wenxi Tian, Yali Su, Khurrum Saleem Chaudri, G.H. Su, Suizheng Qiu (2011). Development of TACOS code for loss of flow accident analysis of SCWR with mixed spectrum core. Progress in Nuclear Energy.DOI
1189. Dawei Zhao, G.H. Su, Zhongshuai Liang, Y.J. Zhang, Wenxi Tian, Suizheng Qiu (2011). Experimental research on transient critical heat flux in vertical tube under oscillatory flow condition. International Journal of Multiphase Flow.DOI
1190. Youjia Zhang, G.H. Su, Suizheng Qiu, Wenxi Tian, Hua Li, Libo Qian, Yong Li, Xiao Yan, Yanping Huang (2011). Numerical research on oscillation of two-phase flow in multichannels under rolling motion. Nuclear Engineering and Design.DOI
1191. Y.P. Zhang, Suizheng Qiu, G.H. Su, Wenxi Tian (2011). A simple novel analysis procedure for IVR calculation in core-molten severe accident. Nuclear Engineering and Design.DOI
1192. Yapei Zhang, Suizheng Qiu, G.H. Su, Wenxi Tian (2011). Design and transient analyses of emergency passive residual heat removal system of CPR1000. Part Ⅰ: Air cooling condition. Progress in Nuclear Energy.DOI
1193. W.W. Wang, G.H. Su, Suizheng Qiu, Wenxi Tian (2011). Thermal hydraulic phenomena related to small break LOCAs in AP1000. Progress in Nuclear Energy.DOI
1194. Y.P. Zhang, Suizheng Qiu, G.H. Su, Wenxi Tian (2011). Analytical model for CHF in narrow gaps with surface orientation effects. Annals of Nuclear Energy.DOI
1195. Xinghui Cai, G.H. Su, Suizheng Qiu (2011). Upwinding meshfree point collocation method for steady MHD flow with arbitrary orientation of applied magnetic field at high Hartmann numbers. Computers & Fluids.DOI
1196. Wenxing Liu, Wenxi Tian, Yingwei Wu, G.H. Su, Suizheng Qiu, Yanping Huang (2011). ICONE19-43858 An improved critical heat flux prediction model for subcooled and low quality flow boiling under motion condition based on microscopic mechanism. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
1197. Yapei Zhang, Suizheng Qiu, G.H. Su, Wenxi Tian, Jianhua Cao, Donghua Lu, Xiangang Fu (2011). ICONE19-43763 DESIGN AND TRANSIENT ANALYSES OF PASSIVE EMERGENCY FEEDWATER SYSTEM OF CPR1000 : PART I: AIR COOLING CONDITION. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
1198. Hua Li, Suizheng Qiu, G.H. Su, Wenxi Tian, Youjia Zhang (2011). ICONE19-43215 NUMERICAL RESEARCH ON THE THERMAL HYDRAULICS OF THE COOLANT IN A PEBBLE BED REACTOR CORE BY CFD. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
1199. Weifeng Ni, Suizheng Qiu, G.H. Su, Wenxi Tian, Yingwei Wu (2011). ICONE19-43372 Numerical Simulation of Opposing Mixed Convection Heat Transfer of Lithium-Lead in a Vertical Square Channel with Heat Source. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
1200. Donglin Zhao, G.H. Su, Zhongshuai Liang, Y.J. Zhang, Suizheng Qiu (2011). ICONE19-43196 Prediction of Periodic Dryout Critical Heat Flux under Flow Oscillation Condition. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
1201. 文彦，高超，秋穗正，苏光辉（2010）. 矩形窄缝通道内水稳态和瞬态流动换热特性实验. 《核动力工程》.
1202. 巫英伟，庄程军，苏光辉，秋穗正（2010）. 压水堆核动力系统瞬态热工水力特性分析仿真软件. 《核动力工程》.
1203. 赵大卫，苏光辉，秋穗正（2010）. 竖直圆管内脉动流量下临界热流密度预测. 《核动力工程》.
1204. 赵大卫，苏光辉，张友佳，梁振辉，秋穗正（2010）. 流量正弦脉动下圆管内单相换热的实验研究. 《核动力工程》.
1205. 陈荣华，苏光辉，秋穗正（2010）. 池式沸腾和流动沸腾的人工神经网络研究. 《核动力工程》.
1206. 卢庆，秋穗正，叶忠昊，苏光辉（2010）. 矩形窄通道空气自然对流换热特性实验研究. 《工程热物理学报》.
1207. 向斌，冯开明，叶兴福，秋穗正（2010）. 中国氦冷固态实验包层氦气实验回路设计分析. 《核聚变与等离子体物理》.
1208. Xinghui Cai, G.H. Su, Suizheng Qiu (2010). Local radial point interpolation method for the fully developed magnetohydrodynamic flow. Applied Mathematics and Computation.DOI
1209. Ronghua Chen, G.H. Su, Wenxi Tian, Suizheng Qiu, Jia Dounan (2010). Development of TSAC1.0 and application to reactivity insertion accident of CARR. Progress in Nuclear Energy.DOI
1210. Ronghua Chen, Wenxi Tian, G.H. Su, Suizheng Qiu, Yuki Ishiwatari, Y. Oka (2010). Numerical investigation on bubble dynamics during flow boiling using moving particle semi-implicit method. Nuclear Engineering and Design.DOI
1211. Xingbo Yang, G.H. Su, Wenxi Tian, Jiayun Wang, Suizheng Qiu (2010). Numerical study on flow and heat transfer characteristics in the rod bundle channels under super critical pressure condition. Annals of Nuclear Energy.DOI
1212. Peng Wang, Libo Qian, Dalin Zhang, Wenxi Tian, G.H. Su, Suizheng Qiu (2010). Study on the Coupled Neutronic and Thermal-Hydraulic Characteristics of the New Concept Molten Salt Reactor. Journal of Engineering for Gas Turbines and Power.DOI
1213. Wen Tian, Suizheng Qiu, G.H. Su, Yuki Ishiwatari, Y. Oka (2010). Numerical Solution on Spherical Vacuum Bubble Collapse Using MPS Method. Journal of Engineering for Gas Turbines and Power.DOI
1214. Y.P. Zhang, Suizheng Qiu, G.H. Su, Wenxi Tian (2010). Analysis of safety margin of in-vessel retention for AP1000. Nuclear Engineering and Design.DOI
1215. Huiming Wei, G.H. Su, Wenxi Tian, Suizheng Qiu, X.B. Yang (2010). Study on the onset of nucleate boiling in narrow annular channel by genetic neural network. International Communications in Heat and Mass Transfer.DOI
1216. R. H. Chen, G.H. Su, Suizheng Qiu, Kenji Fukuda (2010). Prediction of CHF in concentric-tube open thermosiphon using artificial neural network and genetic algorithm. Heat and Mass Transfer.DOI
1217. Yingwei Wu, G.H. Su, Bin Hu, Suizheng Qiu (2010). Study on onset of nucleate boiling in bilaterally heated narrow annuli. International Journal of Thermal Sciences.DOI
1218. Xiaoyu Cai, G.H. Su, Suizheng Qiu, Wenxi Tian (2010). Investigation of Pressure Drop for Fluid Flow Through Porous Media: Application to a Pebble-Bed Reactor. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
1219. Ronghua Chen, Gunaghui Su, Suizheng Qiu (2010). Analysis of CHF Characteristics of Concentric-Tube Open Thermosyphon by Using Artificial Neural Network. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
1220. Y. J. Zhang, G.H. Su, Suizheng Qiu, Han Li (2010). Numerical Research on Oscillation of Two-Phase Flow Under Rolling Motion. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
1221. Rong Hua Chen, Guang Hui Su, Suizheng Qiu (2010). Study on Pool Boiling and Flow Boiling with Artificial Neural Networks. Hedongli gongcheng.
1222. Xinghui Cai, G.H. Su, Suizheng Qiu (2010). Upwinding Meshfree Point Collocation Method for Steady MHD Flow. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
1223. Weifeng Ni, Suizheng Qiu, Guanghui Su, Wenxi Tian (2010). Preliminary Analysis of Three ULOFAs Based on the Dual-Functional Lithium Lead Test Blanket Module Configuration in ITER. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
1224. Xinghui Cai, G.H. Su, Suizheng Qiu (2010). Meshless Local Petrov-Galerkin Method for the Steady Magnetohydrodynamic (MHD) Flow in Rectangular Ducts With Arbitrary Wall Conductivity. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
1225. Qing Gang Lu, Suizheng Qiu, Wenxi Tian, G.H. Su (2010). Investigation on the Accident of Loss of Offsite Power of CARR. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
1226. Xingbo Yang, G.H. Su, Wenxi Tian, Jiayun Wang, Suizheng Qiu (2010). Numerical Study on Flow and Heat Transfer in Concentric and Eccentric Annuli. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
1227. Yapei Zhang, Suizheng Qiu, G.H. Su, Wenxi Tian (2010). A Novel Point Estimate Procedure for IVR Calculations in Core-Molten Severe Accident. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
1228. 卢庆，叶忠昊，秋穗正，苏光辉（2009）. 竖直矩形窄通道空气自然对流换热特性的实验研究. 《西安交通大学学报》.
1229. 赵大卫，苏光辉，田文喜，秋穗正，K. Sugiyama（2009）. 基于人工神经网络分析面朝下加热池式过渡沸腾. 《原子能科学技术》.
1230. 杜东晓，苏光辉，秋穗正（2009）. 曲率对竖直向上环形狭窄通道内环状流特性的影响. 《原子能科学技术》.
1231. 张友佳，苏光辉，秋穗正，郭玉君（2009）. 横摇条件下九通道系统两相流动不稳定性研究. 《原子能科学技术》.
1232. 秋穗正，张大林，苏光辉，田文喜（2009）. 新概念熔盐堆的固有安全性及相关关键问题研究. 《原子能科学技术》.
1233. 扈本学，徐彦峰，苏光辉，秋穗正，赵大卫，巫英伟（2009）. 水平窄缝内多孔介质传热特性研究. 《原子能科学技术》.
1234. 李华，秋穗正，苏光辉，宋小明（2009）. 球床堆内冷却剂流动与传热特性的CFD研究. 《核动力工程》.
1235. 卢庆，张志俭，秋穗正，苏光辉，田文喜（2009）. 板状燃料元件堆芯热工水力特性分析程序开发及验证. 《核动力工程》.
1236. 田文喜，秋穗正，苏光辉，贾斗南，刘兴民，张建伟（2009）. CARR热工水力与安全分析程序TSACC的开发与验证. 《核动力工程》.
1237. 魏会明，苏光辉，秋穗正，杨杏波（2009）. 基于小波分析和遗传算法的沸腾曲线特征点研究. 《原子能科学技术》.
1238. 曾和义，秋穗正，苏光辉（2009）. 环形窄缝通道湍流流动换热特性分析. 《原子能科学技术》.
1239. 彭常宏，秋穗正，苏光辉，贾斗南（2009）. 环形窄缝通道内干涸后摩擦倍增因子的试验研究. 《原子能科学技术》.
1240. Libo Qian, Suizheng Qiu, Dalin Zhang, G.H. Su, Wenxi Tian (2009). Numerical research on natural convection in molten salt reactor with non-uniformly distributed volumetric heat generation. Nuclear Engineering and Design.DOI
1241. Yingwei Wu, G.H. Su, Suizheng Qiu, Chunyi Zhuang (2009). Development of a thermal-hydraulic analysis software for the Chinese advanced pressurized water reactor. Nuclear Engineering and Design.DOI
1242. Hai-Nan Wei, G.H. Su, Wenxi Tian, Suizheng Qiu, W.F. Ni, X.B. Yang (2009). Study on dryout point by wavelet and GNN. Applied Thermal Engineering.DOI
1243. Bin Hu, G.H. Su, Yingwei Wu, K. Sugiyama, Suizheng Qiu (2009). Experimental investigation on narrow gap heat transfer with porous media under downward-facing horizontal heated surface. Nuclear Engineering and Design.DOI
1244. Dalin Zhang, Suizheng Qiu, G.H. Su (2009). Development of a safety analysis code for molten salt reactors. Nuclear Engineering and Design.DOI
1245. Qing Gang Lu, Suizheng Qiu, G.H. Su, Wenxi Tian, Zhonghao Ye (2009). Experimental research on heat transfer of natural convection in vertical rectangular channels with large aspect ratio. Experimental Thermal and Fluid Science.DOI
1246. Huiming Wei, G.H. Su, Suizheng Qiu, Weifeng Ni, Xingbo Yang (2009). Applications of genetic neural network for prediction of critical heat flux. International Journal of Thermal Sciences.DOI
1247. Yingwei Wu, G.H. Su, Suizheng Qiu, Bin Hu (2009). Experimental study on critical heat flux in bilaterally heated narrow annuli. International Journal of Multiphase Flow.DOI
1248. Y.J. Zhang, G.H. Su, X. B. Yang, Suizheng Qiu (2009). Theoretical research on two-phase flow instability in parallel channels. Nuclear Engineering and Design.DOI
1249. Dalin Zhang, Suizheng Qiu, G.H. Su, C.L. Liu (2009). Development of a steady state analysis code for a molten salt reactor. Annals of Nuclear Energy.DOI
1250. Dalin Zhang, Suizheng Qiu, G.H. Su, C.L. Liu, L.B. Qian (2009). Analysis on the neutron kinetics for a molten salt reactor. Progress in Nuclear Energy.DOI
1251. Qing Gang Lu, Suizheng Qiu, G.H. Su (2009). Development of a thermal–hydraulic analysis code for research reactors with plate fuels. Annals of Nuclear Energy.DOI
1252. Junli Gou, Suizheng Qiu, Guanghui Su, Jia Dounan (2009). Thermal Hydraulic Analysis of a Passive Residual Heat Removal System for an Integral Pressurized Water Reactor. Science and Technology of Nuclear Installations.DOI
1253. Mei Wang, Yan Wen, Suizheng Qiu, G.H. Su, Weifeng Ni (2009). Experimental Study on Thermal-Hydraulic Performance of Single-Phase Water Flow in Narrow Rectangular Channel. Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance.DOI
1254. Dongxiao Du, G.H. Su, Suizheng Qiu (2009). Theoretical Calculation of the Critical Heat Flux in Annular Upward Flow in Vertical Narrow Rectangular Channels.DOI
1255. Libo Qian, Suizheng Qiu, Dalin Zhang, G.H. Su (2009). Natural Convection With Non-Uniform Heat Generation in Molten Salt Reactor.DOI
1256. Xiaoyu Cai, Suizheng Qiu, G.H. Su, Changyou Zhao (2009). Steady-State Thermal-Hydraulic Analysis of a Particle-Bedded Boiling Water Reactor.DOI
1257. Han Li, Suizheng Qiu, G.H. Su (2009). Simulation on the Thermal Hydraulics of the Coolant in a Pebble Bed Reactor Core by CFD.DOI
1258. Wenxi Tian, Suizheng Qiu, G.H. Su, Y. Oka (2009). Numerical Solution on Spherical Vacuum Bubble Collapse Using MPS Method. Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance.DOI
1259. 张大林，秋穗正，刘长亮，苏光辉，贾斗南（2008）. 新概念熔盐堆物理计算方法研究及程序设计. 《原子能科学技术》.
1260. 张大林，秋穗正，刘长亮，苏光辉（2008）. 新概念熔盐堆堆芯稳态热工水力计算. 《工程热物理学报》.
1261. 赵大卫，苏光辉，田文喜，秋穗正，K.Sugiyama（2008）. 加热面朝下的池式过渡沸腾实验研究. 《核动力工程》.
1262. 张大林，秋穗正，苏光辉，贾斗南（2008）. 梯形微通道内充分发展层流摩擦阻力特性的数值研究. 《原子能科学技术》.
1263. 曾和义，秋穗正，苏光辉，贾斗南（2008）. 宽高比对矩形窄缝通道内流体温度场的影响. 《核动力工程》.
1264. 田文喜，秋穗正，苏光辉，贾斗南，张建伟（2008）. 中国先进研究堆未能停堆的全厂断电事故分析. 《核动力工程》.
1265. 卢庆，秋穗正，田文喜，苏光辉（2008）. 板状燃料元件堆芯流量分配及不对称冷却计算研究. 《核动力工程》.
1266. 段枫，苏光辉，秋穗正，肖泽军，黄彦平（2008）. 垂直向上流动通道内环状流干涸点的理论研究. 《核动力工程》.
1267. 陈颜静，冯开明，高椿明，盛光召，张国书，秋穗正（2008）. 中国ITER氦冷固态实验包层模块电磁安全分析. 《核聚变与等离子体物理》.
1268. Dalin Zhang, Qiu Suizheng, Changliang Liu, Su Guanghui (2008). Steady state investigation on neutronics of a molten salt reactor considering the flow effect of fuel salt. Chinese Physics C.DOI
1269. Heyi Zeng, Suizheng Qiu, G.H. Su, Jia Dounan (2008). Flow characteristics of single-phase flow in narrow annular channels. Frontiers of Energy and Power Engineering in China.DOI
1270. Qing Gang Lu, Suizheng Qiu, G.H. Su (2008). Flow blockage analysis of a channel in a typical material test reactor core. Nuclear Engineering and Design.DOI
1271. Wenxi Tian, G.H. Su, Gaopeng Wang, Suizheng Qiu, Zejun Xiao (2008). Numerical simulation and optimization on valve-induced water hammer characteristics for parallel pump feedwater system. Annals of Nuclear Energy.DOI
1272. Dalin Zhang, Suizheng Qiu, C Liu, G.H. Su (2008). Steady thermal hydraulic analysis for a molten salt reactor. Nuclear Science and Techniques.DOI
1273. Yun Rui Guo, Suizheng Qiu, G.H. Su, D.N. Jia (2008). The influence of ocean conditions on two-phase flow instability in a parallel multi-channel system. Annals of Nuclear Energy.DOI
1274. Dawei Zhao, G.H. Su, Wenxi Tian, K. Sugiyama, Suizheng Qiu (2008). Experimental and theoretical study on transition boiling concerning downward-facing horizontal surface in confined space. Nuclear Engineering and Design.DOI
1275. Dalin Zhang, Changliang Liu, Libo Qian, G.H. Su, Suizheng Qiu (2008). Numerical Research on Steady Coupling of Neutronics and Thermal-Hydraulics for a Molten Salt Reactor.DOI
1276. Wenxi Tian, G.H. Su, Suizheng Qiu, Gaopeng Wang, Qing Gang Lu (2008). Water Hammer Characteristics for Parallel Pumps Water Supply Systems.DOI
1277. Dawei Zhao, G.H. Su, Suizheng Qiu, Wenxi Tian (2008). Prediction of Post-Dryout Heat Transfer in Vertical Annular Channels Using Artificial Neural Network Method. Volume 2: Fuel Cycle and High Level Waste Management; Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition.DOI
1278. Xiaohai Yang, G.H. Su, Suizheng Qiu (2008). Development of Simulation Codes for Some Accidents in Pressurized Water Reactors. Volume 2: Fuel Cycle and High Level Waste Management; Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition.DOI
1279. Qing Gang Lu, Wenxi Tian, Suizheng Qiu, G.H. Su (2008). Steady-State Thermal-Hydraulic Analysis of a Plate Type Reactor. Volume 2: Fuel Cycle and High Level Waste Management; Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition.DOI
1280. Y. J. Zhang, G.H. Su, Suizheng Qiu, Xiaoping Yang (2008). Research on Two-Phase Flow Instability in Parallel Multi-Channel Under Rolling Motion Condition. Volume 2: Fuel Cycle and High Level Waste Management; Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition.DOI
1281. Dalin Zhang, Suizheng Qiu (2008). Steady Thermal Hydraulics Analysis for a Graphite-Moderated Channel Type Molten Salt Reactor. Volume 4: Structural Integrity; Next Generation Systems; Safety and Security; Low Level Waste Management and Decommissioning; Near Term Deployment: Plant Designs, Licensing, Construction, Workforce and Public Acceptance.DOI
1282. 曾和义，秋穗正，苏光辉，贾斗南（2007）. 环形窄缝通道单相流动特性研究. 《原子能科学技术》.
1283. 吴鸽平，秋穗正，苏光辉，贾斗南（2007）. 套管直流蒸汽发生器流动不稳定性研究. 《原子能科学技术》.
1284. 杨晓强，秋穗正，贾晓鸿，尹海峰，贾斗南，卢冬华（2007）. 水平矩形窄缝通道内水沸腾换热的实验研究. 《核动力工程》.
1285. 田文喜，秋穗正，王甲强，苏光辉，贾斗南，张建伟（2007）. 中国先进研究堆稳态自然循环能力分析. 《核动力工程》.
1286. 吴鸽平，秋穗正，苏光辉，贾斗南（2007）. 环形窄缝通道内流动不稳定性试验研究. 《核动力工程》.
1287. 郭赟，秋穗正，苏光辉，张友佳，贾斗南（2007）. 摇摆状态下入口段和上升段对两相流动不稳定性的影响. 《核动力工程》.
1288. 贾晓鸿，秋穗正，杨晓强，尹海锋，贾斗南，聂常华（2007）. 水平矩形窄缝通道内水沸腾流动特性实验研究. 《工程热物理学报》.
1289. 樊普，秋穗正，苟军利，贾斗南（2007）. 套管式双面加热蒸汽发生器的热工水力分析. 《原子能科学技术》.
1290. Wu Geping, Qiu Suizheng, Su Guanghui, Tian Wenxi, Jia Dounan (2007). CHF and dryout point in vertical narrow annuli. Nuclear Engineering and Design.DOI
1291. G.H. Su, Feng Duan, Suizheng Qiu, Zejun Xiao, Yanping Huang (2007). Numerical investigation on the dryout point of annular flow in the upward narrow annuli with bilateral heating. Frontiers of Energy and Power Engineering in China.DOI
1292. Wenxi Tian, Suizheng Qiu, Jiangfeng WANG, G.H. Su, D.N. Jia, Junxiao Zhang (2007). Analysis on natural circulation capacity of the CARR. Nuclear Science and Techniques.DOI
1293. Wenxi Tian, Suizheng Qiu, Yun Rui Guo, G.H. Su, Jia Dounan, Tiancai Liu, Jianwei Zhang (2007). Development of a steady thermal-hydraulic analysis code for the China Advanced Research Reactor. Frontiers of Energy and Power Engineering in China.DOI
1294. Wenxi Tian, Suizheng Qiu, Guanghui Su, Jia Dounan, Xingmin Liu, Jianwei Zhang (2007). Thermohydraulic and safety analysis on China advanced research reactor under station blackout accident. Annals of Nuclear Energy.DOI
1295. Yingwei Wu, Guanghui Su, Suizheng Qiu, Ken-ichiro SUGIYAMA (2007). ICONE15-10388 NUMERICAL SIMULATION OF NATURAL CONVECTION HEAT TRANSFER FROM A DOWNWARD-FACING HORIZONTAL ROUND PLATE IN CONFINED SPACE. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
1296. Dalin Zhang, Suizheng Qiu, Guanghui Su, Jia Dounan (2007). ICONE15-10451 Evaluation of Static Thermodynamic Properties of the Ternary Molten Salt System Li, Na, Be/F, Based on the Modified Peng-Robinson Equation. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
1297. 苟军利，秋穗正，樊普，贾斗南（2006）. 非能动余热排出系统的瞬态特性数值分析. 《西安交通大学学报》.
1298. 吴鸽平，秋穗正，苏光辉，贾斗南（2006）. 蒸汽发生器强迫循环流动不稳定性分析. 《核动力工程》.
1299. 苟军利，秋穗正，贾斗南，苏光辉（2006）. 新型压水堆自然循环特性计算分析. 《西安交通大学学报》.
1300. 张大林，秋穗正，苟军利，贾斗南（2006）. 新型氮气稳压器系统稳态和瞬态特性研究. 《核动力工程》.
1301. 田文喜，秋穗正，贾斗南（2006）. 环形窄缝通道内弥散流换热的理论计算. 《西安交通大学学报》.
1302. 曾和义，秋穗正，贾斗南（2006）. 双侧加热环形窄缝通道内单相水的流动传热特性研究. 《核动力工程》.
1303. 曾和义，秋穗正，贾斗南（2006）. 热流密度比对环形窄缝通道内单相水换热特性的影响. 《西安交通大学学报》.
1304. 吴鸽平，秋穗正，苏光辉，贾斗南（2006）. 强迫循环下蒸汽发生器流动不稳定性研究. 《核科学与工程》.
1305. 樊普，秋穗正，贾斗南（2006）. 垂直向上圆管环状流临界热流密度研究. 《核动力工程》.
1306. 田文喜，秋穗正，郭赟，苏光辉，贾斗南，刘天才，张建伟（2006）. 中国先进研究堆稳态热工水力计算程序开发. 《原子能科学技术》.
1307. 郭赟，苏光辉，田文喜，秋穗正，贾斗南，张建伟，刘天才（2006）. 中国先进研究堆自然循环两相流动不稳定性分析. 《原子能科学技术》.
1308. 章春伟，秋穗正，王布雷（2006）. 矩形窄缝通道泡状流向弹状流流型转化研究. 《西安交通大学学报》.
1309. Junli Gou, Suizheng Qiu, G.H. Su, D.N. Jia (2006). Theoretical investigation on the steady-state natural circulation characteristics of a new type of pressurized water reactor. Nuclear Science and Techniques.DOI
1310. Hongzhen Zeng, Suizheng Qiu, D.N. Jia (2006). Investigation on the characteristics of the flow and heat transfer in bilaterally heated narrow annuli. International Journal of Heat and Mass Transfer.DOI
1311. Ge Ping Wu, Suizheng Qiu, Guang Hui Su, Jia Dounan (2006). Analysis of Flow Instabilities in Forced-Convection Steam Generator.DOI
1312. Fan Pu, Suizheng Qiu, G.H. Su, Jia Dounan (2006). An Investigation of Flow, Heat Transfer Characteristic of Annular Flow and Critical Heat Flux in Vertical Upward Round Tube.DOI
1313. Junli Gou, Suizheng Qiu, Guanghui Su, Jia Dounan (2006). Natural Circulation Characteristics of an Integral Pressurized Water Reactor.DOI
1314. Ge Ping Wu, Suizheng Qiu, Guang Hui Su, Jia Dounan (2006). Experimental Research on Dryout Point of Flow Boiling in Narrow Annuli.DOI
1315. Wenxi Tian, Suizheng Qiu, G.H. Su, Jia Dounan, Xingmin Liu (2006). Thermohydraulic and Safety Analysis for CARR Under Station Blackout Accident.DOI
1316. 田文喜，秋穗正，郭赟，苏光辉，贾斗南，刘天才，张建伟（2005）. 中国先进研究堆自然循环程序的开发及应用. 《西安交通大学学报》.
1317. 周涛，秋穗正，贾斗南，苏光辉（2005）. 低温供热堆换热器的实时仿真研究. 《西安交通大学学报》.
1318. 田文喜，秋穗正，郭赟，苏光辉，贾斗南，刘天才，张建伟（2005）. 中国先进研究堆堆芯流量分配计算. 《核科学与工程》.
1319. 田文喜，余方伟，秋穗正，贾斗南，苏光辉，王桂芳（2005）. 场协同理论在平行通道内的数值验证. 《核动力工程》.
1320. 章春伟，秋穗正，严明宇，王布雷，聂常华（2005）. 矩形窄缝通道内水沸腾流型理论研究. 《核动力工程》.
1321. 彭常宏，郭贇，贾斗南，秋穗正，苏光辉，聂常华（2005）. 环形窄缝通道中沸腾压降的实验研究. 《核动力工程》.
1322. 田文喜，秋穗正，贾斗南（2005）. 双面加热环形通道内干涸点的确定. 《工程热物理学报》.
1323. 周涛，贾斗南，苏光辉，秋穗正，杨瑞昌（2005）. 200MW低温供热堆容积补偿器仿真. 《原子能科学技术》.
1324. 严明宇，秋穗正，田文喜，王甲强，贾斗南，卢冬华（2005）. 环形窄缝双面加热通道内欠热沸腾传热实验研究. 《原子能科学技术》.
1325. 杨晓强，苏光辉，苟军利，秋穗正，贾斗南（2005）. 环形窄缝通道内干涸型临界热流密度的理论研究. 《原子能科学技术》.
1326. Peng Changhong, Yun Rui Guo, Qiu Suizheng, Jia Dounan, Nie Changhua (2005). Two-phase flow and boiling heat transfer in two vertical narrow annuli. Nuclear Engineering and Design.DOI
1327. Wenxi Tian, Suizheng Qiu, D.N. Jia (2005). Investigations on post-dryout heat transfer in bilaterally heated annular channels. Annals of Nuclear Energy.DOI
1328. Masatoshi Kondo, Minoru Takahashi, Tadashi Suzuki, Kotaro Ishikawa, Koji Hata, Suizheng Qiu, Hiroshi Sekimoto (2005). Metallurgical study on erosion and corrosion behaviors of steels exposed to liquid lead–bismuth flow. Journal of Nuclear Materials.DOI
1329. 王甲强，贾斗南，郭赟，严明宇，秋穗正，苏光辉，卢冬华（2004）. 环形窄通道内过冷沸腾起始点的实验研究. 《核动力工程》.
1330. 吴鸽平，吴埃敏，郭贇，秋穗正，卢东华（2004）. 环形窄缝通道内流动沸腾干涸点的研究. 《西安交通大学学报》.
1331. 李志辉，吴埃敏，贾斗南，秋穗正，聂常华（2004）. 低质量流速下环形通道内干涸后传热实验研究. 《西安交通大学学报》.
1332. Wenxi Tian, Suizheng Qiu, Y. Guo, G.H. Su, Jia Dounan (2004). Development of a thermal-hydraulic analysis code for CARR. Annals of Nuclear Energy.DOI
1333. Aye Aye Myint, Wenxi Tian, Zhihui Li, Suizheng Qiu, Jia Dounan, G.H. Su (2004). Experimental Study on Post-Dryout Heat Transfer of Dispersed Flow in Vertical Narrow Annuli. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
1334. Wenxi Tian, Aye Aye Myint, Zhihui Li, Suizheng Qiu, G.H. Su, Jia Dounan (2004). Experimental Study on Dryout Point in Vertical Narrow Annulus Under Low Flow Conditions. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
1335. 张弛，吴埃敏，苏光辉，彭常宏，秋穗正，褚俊，贾斗南，聂常华（2003）. 窄缝环形通道内饱和沸腾的实验研究. 《核动力工程》.
1336. 彭常宏，吴埃敏，郭贇，贾斗南，秋穗正，苏光辉，聂常华（2003）. 窄缝环形通道内单相液体传热和压降的实验研究. 《核动力工程》.
1337. 王增辉，贾斗南，刘瑞兰，苏光辉，秋穗正（2003）. 环形狭缝膜态沸腾弥散两相流动特性研究. 《核科学与工程》.
1338. Suizheng Qiu, Minoru Takahashi, Jia Dounan, Guanghui Su (2003). Density Wave Instability of Sodium Boiling Two-phase Flow in a Vertical Annulus at Low Pressure. Journal of Nuclear Science and Technology.DOI
1339. 张维忠，贾斗南，秋穗正（2002）. 高温气冷堆一回路舱室的辐射换热计算模型. 《核动力工程》.
1340. 王增辉，贾斗南，刘瑞兰，苏光辉，秋穗正（2002）. 环形狭缝通道内干涸后传热研究. 《核科学与工程》.
1341. 王增辉，刘瑞兰，贾斗南，苏光辉，秋穗正（2002）. 环形狭缝过热气传热试验研究. 《西安交通大学学报》.
1342. Suizheng Qiu, Minoru Takahashi, G.H. Su, Jia Dounan (2002). Experimental Study on Heat Transfer of Single-Phase Flow and Boiling Two-Phase Flow in Vertical Narrow Annuli. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
1343. Minoru Takahashi, Hiroshi Sekimoto, Kotaro Ishikawa, Naoki Sawada, Tadashi Suzuki, Koji Hata, Susumu Yoshida, Suizheng Qiu, Toyohiko Yano, Masamitsu Imai (2002). Experimental Study on Flow Technology and Steel Corrosion of Lead-Bismuth. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
1344. Minoru Takahashi, Suizheng Qiu, Shin-ichi Kitagawa (2002). Droplets Behavior of Hollow-Cone Spray in a Non-Condensable Environment. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
1345. Suizheng Qiu, Minoru Takahashi, Jia Dounan (2002). Experimental Study on Density Wave Instability of Sodium Boiling Two-Phase Flow in an Annulus. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
1346. 张维忠，秋穗正，曾科，廖义香，贾斗南，邱立清，彭凤，林正兴（2001）. 高通量工程试验堆堆芯流量分配计算. 《核动力工程》.
1347. 周涛，秋穗正，贾斗南，苏光辉（2001）. 模糊数学方法在压水堆热工水力分析中的应用. 《西安交通大学学报》.
1348. 周涛，苏光辉，张维忠，秋穗正，贾斗南（2001）. 用灰色系统理论预测环形通道内液钠的临界热流密度. 《原子能科学技术》.
1349. 廖义香，秋穗正，张维忠，郭玉君，贾斗南（2001）. 200MW低温堆余热排出系统安全分析程序研制. 《西安交通大学学报》.
1350. 周涛，贾斗南，王志刚，秋穗正，李晓鸣，张凤琴（2001）. 应用未确知数学研究环形通道内液钠流动的相关参数. 《西安交通大学学报》.
1351. 王增辉，刘瑞兰，贾斗南，苏光辉，秋穗正（2001）. 垂直环形狭缝干涸后弥散流换热研究. 《西安交通大学学报》.
1352. 秋穗正，张维忠，廖义香，贾斗南（2001）. 液钠沸腾两相流流型与临界热流密度(CHF)机理实验研究. 《核科学与工程》.
1353. 刘瑞兰，贾斗南，王增辉，苏光辉，秋穗正（2001）. 环形狭缝通道内沸腾换热传热特性的实验研究. 《核科学与工程》.
1354. 廖义香，秋穗正，郭玉君，贾斗南（2001）. 200MW核供热堆余热排出系统排热能力及其影响因素分析. 《原子能科学技术》.
1355. Suizheng Qiu, Minoru Takahashi, Jia Dounan, Guanghui Su (2001). K-2206 Experimental Study on Heat Transfer of Boiling Two-Phase Flow in Narrow Annular Channel. The proceedings of the JSME annual meeting.DOI
1356. 周涛，贾斗南，苏光辉，秋穗正，荣森林（2000）. 微机型压水堆堆芯安全分析程序的开发及若干问题分析. 《核科学与工程》.
1357. 秋穗正，张维忠，黄代顺，贾斗南，曾科，邱立清，彭风，林正兴（2000）. 高通量工程试验堆燃料元件热工水力特性计算. 《核科学与工程》.
1358. 秋穗正，张维忠，廖义香，贾斗南（2000）. 液态钠临界热流密度实验研究. 《原子能科学技术》.
1359. 周涛，苏光辉，秋穗正，贾斗南（2000）. 压水堆堆芯安全分析程序实时仿真的分析研究. 《西安交通大学学报》.
1360. 周涛，苏光辉，秋穗正，郭玉君，贾斗南（2000）. 多区变节点压水堆堆芯通用安全分析程序的研制. 《西安交通大学学报》.
1361. 苏光辉，郭玉君，张金玲，秋穗正，贾斗南，王騃（1999）. 两相自然循环流动不稳定性脉动周期的实验和理论研究. 《原子能科学技术》.
1362. 秋穗正，NormanC.Johnston（1999）. 秦山三期CANDU核电厂堆芯结构. 《核动力工程》.
1363. 秋穗正，周涛，郭玉君，张金玲，苏光辉，陈炳德，肖泽军（1999）. AC-600应急余热排出系统建模与动态仿真. 《核动力工程》.
1364. 张金玲，郭玉君，苏光辉，秋穗正，贾斗南，喻真烷（1999）. 压水堆稳态自然循环载热能力的研究与分析. 《核科学与工程》.
1365. 解衡，张金玲，贾斗南，苏光辉，喻真烷，秋穗正（1998）. 一体化压水堆蒸汽发生器的热工水力瞬态特性分析. 《核动力工程》.
1366. 苏光辉，郭予飞，郭玉君，张金玲，秋穗正，贾斗南，喻真烷（1998）. 垂直上升管内密度波不稳定性的研究. 《核动力工程》.
1367. 苏光辉，张金玲，郭玉君，秋穗正，贾斗南，喻真烷，郭予飞（1998）. 两相自然循环密度波不稳定性的实验研究. 《核科学与工程》.
1368. 苏光辉，郭玉君，张金玲，秋穗正，贾斗南，喻真烷（1998）. 两相自然循环流动第1类密度波不稳定性的理论研究. 《西安交通大学学报》.
1369. 解衡，张金玲，贾斗南，秋穗正，喻真烷，苏光辉，郭玉君（1997）. 直管式直流蒸汽发生器的热工水力特性分析与计算. 《核科学与工程》.
1370. 张金玲，郭玉君，苏光辉，秋穗正，贾斗南，喻真烷（1997）. 非能动应急堆芯余热排出系统对核电厂失去厂外电源事故的影响. 《原子能科学技术》.
1371. 秋穗正，张金玲，郭玉君，苏光辉，喻真烷，贾斗南（1997）. 核电厂蒸汽发生器水位控制特性计算研究. 《核动力工程》.
1372. 单建强，秋穗正，朱继洲，张贵勤（1997）. 安全分析用钠物性偏导数公式的推导研究. 《核动力工程》.
1373. 张金玲，郭玉君，苏光辉，秋穗正，贾斗南，喻真烷（1997）. 压水反应堆稳态自然循环载热能力的研究与分析. 《西安交通大学学报》.
1374. 侯英东，秋穗正，单建强，贾斗南，褚俊（1997）. 液态金属钠两相流动压降特性实验研究. 《西安交通大学学报》.
1375. 苏光辉，何斌，郭玉君，张金玲，秋穗正，贾斗南，喻真烷（1996）. 低温堆工况下流动不稳定性的判别准则. 《西安交通大学学报》.
1376. 苏光辉，喻真烷，张金玲，郭玉君，秋穗正，贾斗南（1996）. 在中压回路上模拟小破口失水事故喷放阶段瞬态热工水力特性. 《核动力工程》.
1377. 张金玲，郭玉君，秋穗正，苏光辉，贾斗南，喻真烷，陈学俊（1994）. 船用压水核反应堆系统自然循环分析. 《辐射防护通讯》.
1378. 苏光辉，喻真烷，郭玉君，张金玲，秋穗正，贾斗南（1994）. 小破失水事故喷放阶段临界时间的实验研究和理论计算. 《辐射防护通讯》.
1379. 黄彦平，贾斗南，肖泽军，秋穗正（1993）. 高温液态金属钠-钠热交换装置的优化设计研究. 《动力工程学报》.
1380. 秋穗正，贾斗南，喻真烷，黄彦平，褚俊（1993）. 环形通道内液钠沸腾机理实验研究. 《核科学与工程》.

预印本

1. Kou Minghai, Xinkun Xiao, Songjiao Yu, Ronghua Chen, Pingting Jiang, Dai Mingliang, Kui Zhang, Yingwei Wu, Wenxi Tian, Suizheng Qiu (2025). Development and Application of a Fission Gas Release Mechanism Model Based on Fuel Performance Analysis Code Froba. SSRN Electronic Journal.DOI
2. Huifang Zhang, Yapei Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2025). The Condensation Heat Transfer Coefficient of Vertical Tube Prediction Based on Machine Learning. SSRN Electronic Journal.DOI
3. Chunxiao Yu, Wenshu Li, Zhiwen Dai, Chenglong Wang, Suizheng Qiu, Wenxi Tian (2025). Coupled Cfd-Dem Simulation of Impurity Deposition Insteam Generator Throttle Device. SSRN Electronic Journal.DOI
4. Liangguo Li, Qianhua Su, Zongbao Nan, Jianming YU, Donghua Lu, Xianghui Lu, Yingwei Wu, Suizheng Qiu, Xin Wang, Jiyong Liu (2025). Experimental Research on Thermal-Hydraulic Characteristics of Generation Iii Pwr Under Loca Conditions. SSRN Electronic Journal.DOI
5. Yang Wang, Xinyu Li, Dalin Zhang, Bin Wang, Pengrui Qiao, Wenxi Tian, Suizheng Qiu, Guanghui Su (2025). Simulation of Supercritical Carbon Dioxide Jet Based on RK-DGSEM Numerical Method. SSRN Electronic Journal.DOI
6. Dong Mao, Kui Zhang, Binzhuo Xia, Fanting Xia, Wenxi Tian, Suizheng Qiu (2024). Analysis of Chf with Single Rod Under Extremely Low Flow and Static Conditions. SSRN Electronic Journal.DOI
7. Xindi LV, Dalin Zhang, Gongle Song, G.H. Su, Wenxi Tian, Suizheng Qiu (2024). Experimental and Numerical Simulation Study on Critical Heat Flux in Narrow Rectangular Channels. SSRN Electronic Journal.DOI
8. Sihai CUI, Haitao Chen, Xinkun Xiao, Ronghua Chen, Kui Zhang, Suizheng Qiu, Wenxi Tian (2024). Development of Ccfl Prediction Model for Pwr Reactor Pressurizer Surge Line Based on Multi-Step Lstm Model. SSRN Electronic Journal.DOI
9. Dianqiang Jiang, Jian Deng, Da‐Lin Zhang, Xingguang Zhou, Changzhi Xiao, Wenxi Tian, Suizheng Qiu, G.H. Su (2024). Evaluation of a Numerical Model for Predicting Flow and Heat Transfer in a Hexagonal Helical Cruciform Seven-Rods Bundle and Analysis of Rod Bundle Size Independence. SSRN Electronic Journal.DOI
10. Xingguang Zhou, Dalin Zhang, Xinyu Li, Hongxing Yu, Wenxi Tian, Suizheng Qiu, G.H. Su (2024). The Property of Grid Resolution for Turbulence Structure Analysis in Direct Numerical Simulation with Spectral Element Method. SSRN Electronic Journal.DOI
11. Bo Wang, Xinyu Li, Xingguang Zhou, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2024). Research on Least Squares Solver for Physics-Informed Neural Network in Thermal-Hydraulic Analysis of Nuclear Reactors. SSRN Electronic Journal.DOI
12. Dalin Zhang, Bingqian Zhang, Shichang YUN, Ronghua Chen, Wenxi Tian, Suizheng Qiu, G.H. Su, Xinze Li (2024). Study on the Characteristics of Dual Heat Source Brayton Cycle. SSRN Electronic Journal.DOI
13. Zimian Duan, Jing Zhang, G.H. Su, Yingwei Wu, Binqian Li, Mingjun Wang, Yanan He, Wenxi Tian, Suizheng Qiu (2023). Optimization Analysis of Nuclear Thermal Coupling for a Small Nuclear Thermal Propulsion (Sntp) Reactor. SSRN Electronic Journal.DOI
14. Shuo Liu, Jin Zhao, Chenglong Wang, Dalin Zhang, Wenxi Tian, Suizheng Qiu, Guanghui Su, Jun Yang (2023). Development and Verification of Safety Analysis Code to Model and Simulate Steam Power Conversion System in Sodium-Cooled Fast Reactor. SSRN Electronic Journal.DOI
15. Xinyang Zhu, Ronghua Chen, Jinshun Wang, Yuhang Niu, Yingwei Wu, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G.H. Su (2023). Development and Validation of Fully-Coupled Subchannel Analysis Code for Lmr within the Moose Framework. SSRN Electronic Journal.DOI
16. Zimian Duan, Jing Zhang, Zichao Han, Mingjun Wang, Yingwei Wu, Yanan He, Wenxi Tian, Suizheng Qiu, Guanghui Su (2022). Nuclear Thermal Coupling Optimization of Baffled Ntp Reactor. SSRN Electronic Journal.DOI
17. Yin Zhang, Jingyu NIE, Chenglong Wang, Kailun Guo, Wenxi Tian, Guanghui Su, Suizheng Qiu (2022). Neutronic/Thermal-Hydraulic Coupling Analysis of Heat Pipe Reactor Nuster-100 Based on Comsol. SSRN Electronic Journal.DOI
18. Yixin Zhang, Jiaxin Zhang, Chenglong Wang, Wenxi Tian, Suizheng Qiu, Guanghui Su (2022). Validation of Lead-Bismuth Thermal Hydraulic Facilities Based on Modified Relap5. SSRN Electronic Journal.DOI
19. Yun Wang, Junmei Wu, Xiao Yan, G.H. Su, Suizheng Qiu (2021). An Innovative Method for the Theoretical Investigation on the Critical Heat Flux of Nanofluid Flow Boiling With Nanoparticle Deposition. SSRN Electronic Journal.DOI

书籍章节

1. Zeqin Zhang, Chenglong Wang, Kailun Guo, Suizheng Qiu, G.H. Su, Wenxi Tian (2024). Microreactors. Elsevier eBooks.DOI
2. Chao Tan, Suizheng Qiu, Chenglong Wang, Zeqin Zhang, Zhengquan Xie, Fei Li (2023). Study on the System Simulation for the Heat Pipe Failure Transient of Heat Pipe Cooled Reactor. Springer proceedings in physics.DOI
3. Xingguang Zhou, Dalin Zhang, Xinyu Li, Xin Min, Wenqiang Wu, Lei Zhou, Wenxi Tian, Suizheng Qiu (2023). Neutronics and Thermal-Hydraulics Coupling Analysis of Integral Inherently Safe Fluoride-Salt-Cooled High-Temperature Advanced Reactor - Fustar. Springer proceedings in physics.DOI
4. Xinyu Li, Dalin Zhang, Xinze Li, Xingguang Zhou, Xinan Wang, Tongan Yang, Wenxi Tian, Suizheng Qiu (2023). An Anisotropic Porous Model for Heat Exchanger Modeling of Fluoride-Salt-Cooled High-Temperature Advanced Reactor -- FuSTAR. Springer proceedings in physics.DOI
5. Yongjiang Wen, Chenglong Wang, Wenxi Tian, G.H. Su, Suizheng Qiu (2023). Numerical Study on External Environmental Radiation of Nuclear Ramjet Reactor. Springer proceedings in physics.DOI
6. Chao Tan, Fuchang Shan, Suizheng Qiu, Chenglong Wang, Zeqin Zhang (2023). Development of Design and Verification Platform for Heat Pipe Cooled Nuclear Reactor. Springer proceedings in physics.DOI
7. Jianghan Fu, Jin Hao Zhao, Chenglong Wang, Zhiwen Dai, Wenxi Tian, Guanghui Su, Suizheng Qiu (2023). High-Fidelity Drum Controller Design of Thermionic Space Nuclear Reactor. Springer proceedings in physics.DOI