张大林

期刊论文

1. 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》.
2. 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》.
3. 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
4. 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》.
5. 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》.
6. Song-Sheng Tang, K. Guo, Mingjun Wang, Dalin Zhang, Cheng-Long Wang, W.-X. Tian (2026). Capillary characteristics and capillary limit of stainless steel screen mesh wicks for sodium-based high-temperature heat pipes. Applied Thermal Engineering.DOI
7. Haoyang Li, Dalin Zhang, Xin-Yu Li, Bo-Yang Jiang, Xiaoyan Yang, Peng-Rui Qiao, W. Tian, Sui-Zheng Qiu, G. 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 (New series).DOI
8. Dianqiang Jiang, Dalin Zhang, Cheng Zhang, Jun-Qiang Zheng, A. Cammi, C. Introini, W. Tian (2026). Thermo-mechanical behavior of helical cruciform fuel with dispersed TRISO particles: A multiphysics simulation study. Annals of Nuclear Energy.DOI
9. Li Deng, Dalin Zhang, Xin-Yu Li, Yiwen Chen, Lei Zhou, W.-X. Tian, Sui-Zheng Qiu, Guang-Hui 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
10. Wenqiang Wu, Dalin Zhang, Zhenyu Feng, Qingshan Chen, W.-X. Tian, Peng-Rui Qiao (2026). A stabilized two-fluid non-equilibrium method for collocated grids using momentum interpolation and flux reconstruction. The Physics of Fluids.DOI
11. Yuzhuo Cai, Dalin Zhang, Yue Lin, Peng Du, Bo Wang, Lina Zhu, W.-X. Tian, Sui-Zheng Qiu, Guang-Hui Su (2026). Thermal-hydraulics analysis of a small lead-cooled fast reactor with reactor vessel cooling system using ACENA. Annals of Nuclear Energy.DOI
12. Xiao-Qing Chen, Xin-Yu Li, Dalin Zhang, Xuanang He, Haikuo Yang, Peng-Rui Qiao, Changzhi Xiao, W. Tian, G. Su, Sui-Zheng Qiu (2026). Simulation study of flow field characteristics of supercritical carbon dioxide jets into lead-bismuth eutectic pool. Applied Thermal Engineering.DOI
13. Shi-Chang Yun, Dalin Zhang, Wen-Xiang Gao, Xin-Yu Li, Xing-Guang Zhou, W.-X. Tian (2026). Hierarchical load-following control of modular fluoride-salt-cooled high-temperature reactor with supercritical carbon dioxide Brayton cycle. Applied Thermal Engineering.DOI
14. Shuo Liu, Wenshu Li, Cheng-Long Wang, Dalin Zhang, W. Tian, Tai Shi, Manzi He (2026). Numerical investigation on convective heat transfer performance of liquid lithium in both a round tube and a 19-rod bundle channel. International journal of thermal sciences.DOI
15. Haoyue Jiao, Dalin Zhang, Kun-Feng Li, Xiaoyu Wang, Dianqiang Jiang, Jiaxu Feng, Peng-Rui Qiao (2026). Experimental study on the thermal stratification characteristics in the upper plenum of lead-bismuth fast reactors. International journal of thermal sciences.DOI
16. Haoyang Li, Hongda Wang, Zhenyu Feng, Dalin Zhang, Xiangyu Yan, W. Tian (2026). Development of a three-dimensional analysis code for sodium fire accidents based on unstructured grid and FVM. Annals of Nuclear Energy.DOI
17. 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
18. 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
19. Shuo Guo, X. F. Zhou, Dianqiang Jiang, Xiaoli Wu, Qi Lu, Ting Zhang, Dalin Zhang (2026). A Novel Fuel Element: Helical Annular Fuel and Its Thermal–Hydraulic Characteristics Analysis in a 2 × 2 Bundle. Springer proceedings in physics.DOI
20. 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
21. 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
22. Ruizhi Qi, Hui Liang, Xingguang Zhou, Yang Zhang, Xiaoqing Chen, Hongxing Yu, Chuan Lu, Pengrui Qiao, Dalin Zhang (2026). Derivation and validation of a turbulent Prandtl number model for LBE in rod bundle channels. Nuclear Engineering and Design.DOI
23. 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
24. 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
25. 丁铜伟，张大林，陈硕（2025）. 小型氟盐冷却高温堆燃料元件三维热工流体设计研究. 《原子能科学技术》.
26. 林悦，张大林，刘雅鹏，孙林，李倩，胡艺，易腾，颜安（2025）. 固态燃料熔盐堆FuSTAR核热耦合数值分析. 《核科学与工程》.DOI
27. 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》.
28. 姜殿强，邓坚，张大林，陆祺，张婷，武小莉，田文喜（2025）. 铅铋堆螺旋形燃料流动传热特性数值研究. 《核技术》.
29. 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
30. 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》.
31. 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》.
32. 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》.
33. 陈晓晴，陈广亮，钱浩，孙林，李倩，胡艺，易腾，张大林（2025）. 压水堆燃料棒束域搅混翼流场作用特性研究. 《核技术》.
34. 陈逸文，张大林，冯振宇，贠世昌，王思思，徐财红，贺东钰，王婷（2025）. 基于FRIGG空泡份额实验的LOCUST1.2验证. 《核技术》.
35. 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》.
36. 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
37. 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》.
38. Xin-Yang Zhu, Jinshun Wang, Rong-Hua Chen, Yuhang Niu, Ying-Wei Wu, Dalin Zhang, W.-X. Tian (2025). Development and validation of fully-coupled subchannel analysis code for LMR within the MOOSE framework. Annals of Nuclear Energy.DOI
39. Dianqiang Jiang, Jian Deng, Dalin Zhang, Xing-Guang Zhou, Changzhi Xiao, W. Tian, Jing Zhang, G. Su (2025). 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. International Communications in Heat and Mass Transfer.DOI
40. Shi-Chang Yun, Xin-Yu Li, Dalin Zhang, Ping Song, W.-X. Tian, Suizheng Qiu, Guang-Hui Su (2025). Research on control strategies for rapid load decrease events in fluoride salt reactor-supercritical CO2 Brayton cycle systems. Nuclear Engineering and Design.DOI
41. Yupeng Yang, Dingsheng Lu, Cheng-Long Wang, Dalin Zhang, S. Qiu, G. Su, W. Tian (2025). Numerical study on heat transfer characteristics of LBE cross flow tube bundle under rolling conditions. Annals of Nuclear Energy.DOI
42. Xing-Guang Zhou, Dalin Zhang, Xin-Yu Li, Hong-Xing Yu, W.-X. Tian, Sui-Zheng Qiu, Guang-Hui Su (2025). DNS study of turbulent heat transfer with different Prandtl numbers under constant wall-temperature difference condition. Progress in nuclear energy (New series).DOI
43. Yiwen Chen, Dalin Zhang, Dianqiang Jiang, Wei Li, Qi Lu, W. Tian, S. Qiu, G. Su (2025). 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
44. Xin-Ze Li, Bing-Qian Zhang, Shi-Chang Yun, Rong-Hua Chen, Dalin Zhang, W. Tian, Sui-Zheng Qiu, G. Su (2025). Comprehensive analysis of dual-heat-source Brayton cycle. Applied Thermal Engineering.DOI
45. Bo Wang, Xin-Yu Li, Xing-Guang Zhou, Dalin Zhang, W.-X. Tian, Suizheng Qiu, Guang-Hui Su (2025). Research on least-square solver for physics-informed neural network in thermal-hydraulic analysis of nuclear reactors. Annals of Nuclear Energy.DOI
46. Mei-yin Zheng, Ping Chen, Dalin Zhang, W.-X. Tian, Guang-Hui Su (2025). Performance of sodium cooled traveling wave reactor core with axial fuel shuffling strategy. International Journal of Advanced Nuclear Reactor Design and Technology.DOI
47. Yue Lin, Dalin Zhang, Yu-Tong Chen, Xi-Si Zhang, Jian Deng, W.-X. Tian, Sui-Zheng Qiu, Guang-Hui Su (2025). Preliminary development and validation of ACENA code for melting and freezing behavior simulation. Annals of Nuclear Energy.DOI
48. Zhenyu Feng, Dalin Zhang, Wenqiang Wu, Haodong Guo, Xi-Lin Zhang, Xiaoyu Wang, Jian Deng, W.-X. Tian, Sui-Zheng Qiu, G. Su (2025). Numerical Study on the Thermal Stratification Characteristics of the Primary System for Lead-based Cooled Fast Reactor. Nuclear Engineering and Technology.DOI
49. Bo Wang, Shuo Guo, Dalin Zhang, W.-X. Tian, Sui-Zheng Qiu, Guang-Hui Su (2025). Sodium side inlet flow distribution characteristics of the steam generator in China demonstration fast reactor. Nuclear Techniques.DOI
50. Dingsheng Lu, Xiao Pang, Han-Rui Qiu, Yupeng Yang, Cheng-Long Wang, Dalin Zhang, Suizheng Qiu (2025). Advanced CFD analysis of impurity formation and transport in liquid Lead-Bismuth Eutectic (LBE) loop systems. Annals of Nuclear Energy.DOI
51. Yue Lin, Dalin Zhang, Yuzhuo Cai, Yapeng Liu, Peng Du, Zhixin Niu, Bo Wang, W. Tian, Sui-Zheng Qiu, Guang-Hui 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 (New series).DOI
52. Wenqiang Wu, Tao Huang, Peng Du, Zhenyu Feng, Dalin Zhang, Lei Zhou, G. Song, Jian Deng, Zhi-Fang Qiu, W. Tian, Sui-Zheng Qiu, Guang-Hui 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
53. Yue Lin, Dalin Zhang, Yuzhuo Cai, Yapeng Liu, Peng Du, Peng-Rui Qiao, W.-X. Tian, Sui-Zheng Qiu, Guang-Hui Su (2025). Numerical Study on material behavior and core temperature field evolution under CDAs in LFR. Nuclear Engineering and Technology.DOI
54. Yu-Tong Chen, Dalin Zhang, Yue Lin, Dingkun Wang, Zhenyu Feng, W. Tian, S. Qiu, G. 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
55. Dingsheng Lu, Xiao Pang, Yupeng Yang, Cheng-Long Wang, Dalin Zhang, Suizheng Qiu (2025). Comprehensive analysis of oxygen mass transfer and impurity dynamics in oxygen-controlled ELSY lead-cooled reactors. Progress in nuclear energy (New series).DOI
56. Wenqiang Wu, Tao Huang, Peng Du, Dalin Zhang, Lei Zhou, Bo Wang, Jian Deng, Zhi-Fang Qiu, W. Tian, Sui-Zheng Qiu, Guang-Hui 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
57. Xing-Guang Zhou, Dalin Zhang, Xin-Yu Li, Wentao Guo, Hong-Xing Yu, W.-X. Tian, Sui-Zheng Qiu, Guang-Hui 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
58. Dianqiang Jiang, Jian Deng, Dalin Zhang, Qi Lu, Ting Zhang, Xiao-Li Wu, W.-X. Tian (2025). Numerical study on flow and heat transfer characteristics of helical fuel in lead-bismuth reactor. Nuclear Techniques.DOI
59. Yihao Yang, Yiheng Fei, Cheng-Long Wang, Dalin Zhang, Jing Zhang, W. Tian, Sui-Zheng Qiu, Guang-Hui Su (2025). Experimental study on the radiative heat transfer characteristics of individual droplets in space liquid droplet radiators. Applied Thermal Engineering.DOI
60. Xin-Ze Li, Bing-Qian Zhang, Chengcheng Tong, Rong-Hua Chen, Dalin Zhang, W.-X. Tian, Sui-Zheng 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
61. Shuo Guo, Xing-Guang Zhou, Dalin Zhang, Changzhi Xiao, Zhixin Niu, W.-X. Tian, Sui-Zheng Qiu, G. Su (2025). High-fidelity 3D neutronics and thermal-hydraulics coupling analysis of a liquid metal-cooled fast reactor. Annals of Nuclear Energy.DOI
62. Xing-Guang Zhou, Dalin Zhang, Xin-Yu Li, Hong-Xing Yu, W.-X. Tian, Sui-Zheng Qiu, Guang-Hui Su (2025). Mixed convection in horizontal channel with unstable stratification for low-Prandtl-number fluids. The Physics of Fluids.DOI
63. Yiwen Chen, Qi Lu, Liu Changwen, Wei Li, Dalin Zhang, G.H. Su (2025). Computational homogenization of thermomechanical properties for Fully Ceramic Microencapsulated fuel with 3D printed SiC matrix. Annals of Nuclear Energy.DOI
64. 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》.
65. 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》.
66. 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》.
67. 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》.
68. 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》.
69. 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》.
70. 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》.
71. 张大林（2024）. 熔盐堆热工水力及安全分析.
72. 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》.
73. Xing-Guang Zhou, Dalin Zhang, Xin-Yu Li, Xindi Lv, Dianqiang Jiang, W. Tian, S. Qiu (2024). Preliminary conceptual design with neutronics and thermal-hydraulics assessments of FuSTAR. Annals of Nuclear Energy.DOI
74. Yue Lin, Dalin Zhang, Yu-Tong Chen, Xi-Si Zhang, Jian Deng, Peng Du, W.-X. Tian, Sui-Zheng Qiu, G. Su (2024). Numerical study on the impact characteristics of molten lead-bismuth droplets into water. Nuclear Engineering and Design.DOI
75. Lei Zhou, Dalin Zhang, Yapeng Liu, Yu Liang, Bo Wang, W.-X. Tian, Sui-Zheng Qiu, Guang-Hui Su (2024). Direct numerical simulation of sodium in vertical channel flow: From forced convection to natural convection at friction Reynolds number 180. The Physics of Fluids.DOI
76. Yu-Tong Chen, Dalin Zhang, Zhenyu Feng, Yue Lin, W.-X. Tian, Sui-Zheng Qiu, Guang-Hui Su (2024). Numerical Investigation of Postulated Steam Generator Tube Rupture Accident in a Lead-Cooled Fast Reactor. Volume 11: Student Paper Competition.DOI
77. Xin-Ze Li, Rong-Hua Chen, Bing-Qian Zhang, Kui Zhang, Dalin Zhang, W.-X. Tian, Sui-Zheng Qiu, Guang-Hui Su (2024). Preliminary Study on Laser Inertial Confinement Fusion Reactor Energy Transfer. Volume 11: Student Paper Competition.DOI
78. Shuo Liu, Zhao Jin, Cheng-Long Wang, Dalin Zhang, W. Tian, S. Qiu, G. Su, Jun Yang (2024). Development of modular dynamic code for steam power conversion system in sodium-cooled fast reactor. Progress in nuclear energy (New series).DOI
79. Yapeng Liu, Dalin Zhang, Lei Zhou, Kailong Chen, W. Tian, S. Qiu, G. Su (2024). Analysis of the effect of thermal stratification on the natural circulation decay heat removal of sodium-cooled fast reactor. Progress in nuclear energy (New series).DOI
80. Shuowang Fan, Yu-Tong Chen, Dalin Zhang, Xiaoli Wu, W.-X. Tian, Sui-Zheng Qiu, Guang-Hui 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. Volume 6: Thermal-Hydraulics and Safety Analysis.DOI
81. Yiwen Chen, Dalin Zhang, Dianqiang Jiang, Jian Deng, Xi-Si Zhang, Xin'an Wang, W. Tian, S. Qiu, G. Su (2024). Thermal-hydraulic characteristics of helical cruciform single rod based on CFD investigation. Annals of Nuclear Energy.DOI
82. Xindi Lv, Dalin Zhang, Xin-Yu Li, Xing-Guang Zhou, Dianqiang Jiang, G. Su, W. Tian, S. Qiu (2024). Study on the safety characteristics of fluoride-salt-cooled high-temperature advanced reactor. Annals of Nuclear Energy.DOI
83. Xing-Guang Zhou, Dalin Zhang, Xin-Yu Li, Jian Deng, W. Tian, S. Qiu, G. Su, Xiaoqiang He, Hong-Xing Yu (2024). Development of a neutron space–time kinetics solver with improved quasi-static method based on OpenFOAM. Nuclear Engineering and Design.DOI
84. Zhipeng Liu, W. Tian, Cheng-Long Wang, Dalin Zhang, Kui Zhang, S. Qiu, G. 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
85. Shi-Chang Yun, Dalin Zhang, Xin-Yu Li, Xindi Lv (2024). Dynamic Modeling and Characteristic Analysis of sCO2 Brayton Cycle System. Volume 11: Student Paper Competition.DOI
86. Rong Zhang, Dalin Zhang, Yu Liang, Jinshun Wang, Jian Deng, Xi-Si Zhang, Zhixin Niu, W. Tian, S. Qiu, Qian Luo (2024). Subchannel thermal–hydraulic analysis of a wire-wrapped 19-pin rod bundle in the NACIE-UP facility. Annals of Nuclear Energy.DOI
87. Xin-Yu Li, Dalin Zhang, Dianqiang Jiang, Xing-Guang Zhou, Xindi Lv, W. Tian, S. Qiu, G. Su (2024). Review, numerical validation, and experiment verification for Definite solution Analogy Theory (DSAT) in thermal-hydraulic scaling. Applied Thermal Engineering.DOI
88. Shuo Guo, Dalin Zhang, Xin-Yu Li, Xuanang He, Hongda Wang, Jian Deng, Xi-Si Zhang, W. Tian, S. Qiu, G. Su (2024). Exergy analysis of biomass and nuclear hydrogen production system. International journal of hydrogen energy.DOI
89. Haoyang Li, Dalin Zhang, Lei Zhou, Jian Deng, W. Tian, G. Su, S. Qiu (2024). Numerical study on benchmark analysis of NACIE-UP facility with uniform and non-uniform power distribution. Annals of Nuclear Energy.DOI
90. Haoyang Li, Dalin Zhang, Hao Qin, Xin-Yu Li, Jian Deng, W. Tian, G. Su, S. Qiu (2024). Study on tritium transport characteristics in fluoride-salt-cooled high-temperature advanced reactor. International journal of hydrogen energy.DOI
91. Jia-Rui Zhang, Cheng-Long Wang, Zhixing Tian, K. Guo, Dalin Zhang, W.-X. Tian, Sui-Zheng Qiu, Guang-Hui Su (2024). Design, Development and Testing of Large Diameter High Temperature Alkaline Metal Heat Pipe. Volume 11: Student Paper Competition.DOI
92. Yapeng Liu, Bo Wang, Dalin Zhang, Zhenyu Feng, Xin-Yu Li, W.-X. Tian, Sui-Zheng Qiu, Guang-Hui Su (2024). Study on Radial Thermal-Hydraulic Characteristics of Once-Through Steam Generator of Sodium-Cooled Fast Reactor. Volume 11: Student Paper Competition.DOI
93. Qi-Fan Yu, Ya-Feng Zhao, Yu-Tong Chen, Zhipeng Liu, Cheng-Long Wang, Dalin Zhang, W. Tian, S. Qiu, G. Su (2024). Multiphase simulation of hyperbaric steam-water jet inside liquid Pb-Bi eutectic environment. Annals of Nuclear Energy.DOI
94. Dianqiang Jiang, Dalin Zhang, W. Tian, S. Qiu, G. 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
95. Qi-Fan Yu, Hongjian Guo, S. Qiu, Cheng-Long Wang, Dalin Zhang, W. Tian, G. 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
96. Xing-Guang Zhou, Dalin Zhang, Lei Zhou, Wenqiang Wu, Xi-Si Zhang, W. Tian, S. Qiu, G. Su (2024). Development and validation of a neutron transport solver with <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" altimg="si257.svg" display="inline" id="d1e2599"><mml:msub><mml:mrow><mml:mtext>SP</mml:mtext></mml:mrow><mml:mrow><mml:mn>3</mml:mn></mml:mrow></mml:msub></mml:math> method based o. Progress in nuclear energy (New series).DOI
97. Zhenyu Feng, Dalin Zhang, Yiwen Chen, Yang-Chun Pu, Shi-Chang Yun, Si-Si Wang, Caihong Xu, Dongyu He, Ting Wang, W. Tian, S. Qiu, G. 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
98. Zhenyu Feng, Dalin Zhang, Haoyu Jiao, Yu-Tong Chen, Yue Lin, W.-X. Tian, Sui-Zheng Qiu, Guang-Hui Su (2024). Study on Bubble Migration Characteristics in a Lead-Cooled Fast Reactor After Steam Generator Tube Rupture Accident. Volume 11: Student Paper Competition.DOI
99. Wenqiang Wu, Dalin Zhang, Tao Huang, Lei Zhou, Peng Du, W.-X. Tian, Sui-Zheng Qiu, Guang-Hui Su (2024). Development and Validation of a Two-Phase Flow Solver With Drift-Flux Model Based on OpenFOAM. Volume 11: Student Paper Competition.DOI
100. X. A. Wang, Ximei Liang, Rongshuan Xu, DongYu He, Ting Wang, Dalin Zhang (2024). Numerical investigation on the core thermal hydraulic behavior of pool-type sodium-cooled fast reactor (SFR). Frontiers in Energy Research.DOI
101. 梁禹，王啸宇，邓坚，刘余，宋功乐，钟睿诚，张大林，朱大欢（2023）. 基于子通道思想的液态金属堆盒间流模拟方法研究. 《核动力工程》.
102. 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》.
103. 赵全斌，赵凯，种道彤，刘秀婷，张大林，卓文斌（2023）. 匹配高温氟盐堆的SCO2系统冷端变工况运行特性研究. 《核动力工程》.
104. 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》.
105. 许家源，赵全斌，孙剑锋，刘秀婷，张大林，卓文斌（2023）. 小型氟盐冷却高温堆SCO2布雷顿循环冷端特性研究. 《原子能科学技术》.
106. 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》.
107. Wen Ding, Kui Zhang, Dalin Zhang, Rong-Hua Chen, Zhongyun Ju, Caihong Xu, Ting Wang, W. Tian, S. 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
108. Yupeng Yang, Cheng-Long Wang, Dalin Zhang, W. Tian, S. Qiu, G. 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
109. Bo Wang, Zhenyu Feng, Youchun Chen, Dalin Zhang, Zhiguang Wu, Jun Yu Li, Ming-Yang Li, Ruoxin Ma, Chao Li (2023). Optimization and Improvement of Sodium Heated Once-through Steam Generator Transient Analysis Code Based on the JFNK Algorithm. Energies.DOI
110. Qi-Fan Yu, Ya-Feng Zhao, S. Qiu, Cheng-Long Wang, Dalin Zhang, W. Tian, G. Su (2023). EXPERIMENTAL INVESTIGATION ON STEAM GENERATOR TUBE RUPTURE (SGTR) ACCIDENT OF LEAD-COOLED FAST REACTORS BASED ON LEST FACILITY. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
111. Dianqiang Jiang, Dalin Zhang, Kailong Chen, Xin-Yu Li, Xing-Guang Zhou, W. Tian, S. Qiu, G. 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
112. Qi-Fan Yu, Yu-Liang Fang, Ya-Feng Zhao, S. Qiu, Cheng-Long Wang, Dalin Zhang, W. Tian, G. 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
113. Xing-Guang Zhou, Dalin Zhang, W. Tian, G. Su, S. Qiu (2023). A framework of the transport model for high-order eddy viscosity tensor in two-dimensional turbulent flow.
114. Jin-Lu Huang, Zhixing Tian, Cheng-Long Wang, K. Guo, Dalin Zhang, W. Tian, S. Qiu, G. Su (2023). TRANSIENT THERMAL SAFETY ANALYSIS OF NUSTER-100 REACTOR CORE. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
115. Xin-Yu Li, Dalin Zhang, Xing-Guang Zhou, Xindi Lv, Dianqiang Jiang, W. Tian, S. Qiu, G. 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
116. Lei Zhou, Dalin Zhang, Shi-Bao Wang, Yapeng Liu, Y. Liang, Jing Zhang, W. Tian, S. Qiu, G. Su (2023). Benchmark analysis of the FFTF LOSWOS test #13 with OpenMC and THACS. Annals of Nuclear Energy.DOI
117. Xin-Yu Li, Dalin Zhang, Xing-Guang Zhou, Xindi Lv, Dianqiang Jiang, Zhi-Yuan Wu, Si-Jun Li, W. Tian, S. Qiu, G. Su (2023). Comparison of Dynamical System Scaling and Hierarchical Two-Tiered Scaling Applications with Definite Solution Analogy Theory to the Passive Residual Heat Removal System of Fluoride-Salt-Cooled High-Temperature Advanced Reactor. 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20).DOI
118. Xin-Ze Li, Dalin Zhang, Xin-Yu Li, W. Tian, S. Qiu, G. 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
119. Qi-Fan Yu, S. Qiu, Cheng-Long Wang, Dalin Zhang, W. Tian, G. 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 (New series).DOI
120. Shi-Chang Yun, Dalin Zhang, Xinyu Li, Xing-Guang Zhou, Dianqiang Jiang, Xindi Lv, Wenqiang Wu, Zhenyu Feng, Xin Min, W. Tian, S. Qiu, G. Su (2023). Design, optimization and thermodynamic analysis of SCO2 Brayton cycle system for FHR. Progress in nuclear energy (New series).DOI
121. Dingsheng Lu, Yupeng Yang, Cheng-Long Wang, Dalin Zhang, Peng-Rui Qiao, W. Tian, S. Qiu, G. Su (2023). Corrosion effect analysis on thermal-hydraulics of LBE/water spiral tube steam generator under oxygen-controlled environment. Applied Thermal Engineering.DOI
122. Yu Liang, Dalin Zhang, Jing Zhang, Xiao Liu, Yapeng Liu, Lei Zhou, Yu-Tong Chen, Xiaoyu Wang, W. Tian, S. Qiu, G. Su (2023). A subchannel analysis code SACOS-Na for sodium-cooled fast reactor. Progress in nuclear energy (New series).DOI
123. ikoleta Morelová, Vladimir Kriventsev, Tyler Sumner, A. Moisseytsev, Florent Heidet, David. W. Wootan, A. Casella, J. Nelson, Ivan Di Piazza, H. Hassan, P. Lorusso, Daniele Martelli, Xiaoyan Yang, Jin Wang, Daogang Lu, Dalin Zhang, Antoine Gerschenfeld, S. Kliem, E. Fridman, A. Rineiski, N. Kumaresan, F. Giannetti, A. Petruzzi, Masaaki Tanaka, Jae-Ho Jeong, Jonggan Hong, M. Stempniewicz, S. Tsaun, Andrei Volkov, J. Wallenius, C. Fiorina, K. Mikityuk, R. Vaghetto, O. Omotowa, J. Kelly, J. Lane (2023). IAEA’S COORDINATED RESEARCH PROJECTS ON THERMAL HYDRAULICS OF FAST REACTORS. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
124. Yupeng Yang, Cheng-Long Wang, Dalin Zhang, S. Qiu, G. Su, W. Tian (2023). Heat transfer evaluation of liquid lead-bismuth eutectic cross flow tube bundle: Experimental part. International journal of thermal sciences.DOI
125. 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
126. Xinyu Li, Dalin Zhang, Xindi Lv, Xing-Guang Zhou, W. Tian, S. Qiu, G. Su (2023). Simulation and design of passive residual heat removal system for Fluoride-Salt-cooled high-Temperature Advanced reactor (FuSTAR). Applied Thermal Engineering.DOI
127. Xing-Guang Zhou, Dalin Zhang, Jie Liu, Chao-Yang Lin, Y. Liang, W. Tian, S. Qiu, G. Su (2023). Numerical and experimental analysis of LBE flow and heat transfer characteristics in hexagonal rod bundles. Annals of Nuclear Energy.DOI
128. Hao Qin, C. Fiorina, Ran Zhang, S. Radman, Dalin Zhang, Cheng-Long Wang, W. Tian, S. Qiu, G. Su (2023). Extension of GeN-Foam to modeling of boiling water and validation against the OECD/NRC PSBT benchmark. Nuclear Engineering and Design.DOI
129. Yu-Bing Wang, Jie Li, Dalin Zhang, Wei-Jian Chen, Guang-Ya Zhu (2023). Investigation of the flow boiling performance in mini channel with micro pin fin. Heat and Mass Transfer.DOI
130. Shi-Chang Yun, Dalin Zhang, Xinyu Li, Xuanang He, W. Tian, S. Qiu, G. Su, Quan-Bin Zhao (2023). Superstructure design and optimization on closed Brayton cycle system of fluoride-salt-cooled high-temperature advanced reactor. Applied Energy.DOI
131. Yupeng Yang, Cheng-Long Wang, Dalin Zhang, S. Qiu, G. Su, W. 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
132. Zhixing Tian, Cheng-Long Wang, K. Guo, Dalin Zhang, G. Su, W. Tian, S. Qiu (2023). A review of liquid metal high temperature heat pipes: Theoretical model, design, and application. International Journal of Heat and Mass Transfer.DOI
133. Zhixing Tian, Cheng-Long Wang, Jia-Rui Zhang, Jin-Lu Huang, K. Guo, Dalin Zhang, W. Tian, S. Qiu, G. Su (2023). DEVELOPMENT OF SODIUM HEAT PIPES FOR NUCLEAR SILENT THERMALELECTRICAL REACTOR (NUSTER-100). The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
134. 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
135. Dalin Zhang, Xin-Yu Li, Dianqiang Jiang, Xing-Guang Zhou, Xindi Lv, Shi-Chang Yun, Wenqiang Wu, Xuanang He, Haoyang Li, Xin Min, Kailong Chen, W. Tian, S. Qiu, G. Su, Quanbin Zhao, Yao Fu, Chun Tang, Wen-Bin Zhuo, Jinggang Li, Jiaxu Zuo (2023). Fluoride-salt-cooled high-temperature advanced reactor (FuSTAR): An integrated nuclear-based energy production and conversion system. Energy.DOI
136. 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
137. Xuan’ang He, Dalin Zhang, Xiang Wang (2023). Visualized Numerical Analysis of Fustar Reactor Based on Modelica Language. Springer proceedings in physics.DOI
138. 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
139. 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》.
140. 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》.
141. 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》.
142. 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》.
143. 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》.
144. 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》.
145. 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》.
146. 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》.
147. 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》.
148. 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》.
149. Xin Min, Dalin Zhang, Rongshuan Xu, Shi-Bao Wang, Youchun Chen, Cheng-Long Wang, W. Tian, S. Qiu, G. 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
150. Zetao Wang, Rui-Yu Han, K. Guo, Cheng-Long Wang, Dalin Zhang, W. Tian, S. Qiu, G. Su (2022). Molecular dynamics simulation of the evaporation of liquid sodium film in the presence of non-condensable gas. Annals of Nuclear Energy.DOI
151. Jin-Lu Huang, Cheng-Long Wang, K. Guo, Dalin Zhang, G. Su, W. Tian, S. Qiu (2022). Heat transfer analysis of heat pipe cooled device with thermoelectric generator for nuclear power application. Nuclear Engineering and Design.DOI
152. Yu-Liang Fang, Cheng-Long Wang, W. Tian, Dalin Zhang, G. Su, S. Qiu (2022). Study on high-temperature hydrogen dissociation for nuclear thermal propulsion reactor. Nuclear Engineering and Design.DOI
153. Zhixing Tian, Yu Liu, Cheng-Long Wang, K. Guo, Dalin Zhang, W. Tian, S. Qiu, G. Su (2022). Single/multi‐objective optimization and comparative analysis of liquid‐metal heat pipe. International Journal of Energy Research.DOI
154. Yin Zhang, Xiao-Ming Chai, Cheng-Long Wang, Si-Miao Tang, Dalin Zhang, W. Tian, G. Su, S. Qiu (2022). Thermal-hydraulic analysis of heat pipe reactor experimental device with thermoelectric generators. Progress in nuclear energy (New series).DOI
155. Lin-Yi Yang, Cheng-Long Wang, Hao Qin, Dalin Zhang, W. Tian, G. Su, S. Qiu (2022). Numerical investigation on radiative and evaporative characteristics of a liquid droplet radiator through Monte-Carlo method. Applied Thermal Engineering.DOI
156. Haiwang Yang, Cheng-Long Wang, Dalin Zhang, Jing Zhang, W. Tian, S. Qiu, G. Su (2022). Parameter sensitivity study on startup characteristics of high temperature potassium heat pipe. Nuclear Engineering and Design.DOI
157. Xiao-Rui Yang, Peng-Lei Zhang, Hui Ma, Kehan Liu, Dalin Zhang (2022). Performance Investigation on Rotating Heat Pipes Under High Rotation Speed and Hypergravity. Social Science Research Network.DOI
158. 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
159. Rui-Yu Han, Zetao Wang, K. Guo, Cheng-Long Wang, Dalin Zhang, W. Tian, S. Qiu, G. Su (2022). Experimental investigation of nano-particle deposited wick Structure's heat transfer characteristics. International Journal of Advanced Nuclear Reactor Design and Technology.DOI
160. Zhixing Tian, Jia-Rui Zhang, Cheng-Long Wang, K. Guo, Yu Liu, Dalin Zhang, W. Tian, S. Qiu, G. Su (2022). Experimental Evaluation on Heat Transfer Limits of Sodium Heat Pipe with Screen Mesh for Nuclear Reactor System. Applied Thermal Engineering.DOI
161. Jie Liu, Ping Song, Dalin Zhang, Shi-Bao Wang, Chao-Yang Lin, Yapeng Liu, Lei Zhou, Cheng-Long Wang, W. Tian, S. Qiu, G. Su (2022). Thermal-hydraulic research on rod bundle in the LBE fast reactor with grid spacer. Nuclear Engineering and Technology.DOI
162. Zetao Wang, K. Guo, Cheng-Long Wang, Dalin Zhang, W. Tian, S. Qiu, G. Su (2022). Molecular dynamics study of liquid sodium film evaporation and condensation by Lennard-Jones potential. Nuclear Engineering and Technology.DOI
163. Dianqiang Jiang, Dalin Zhang, Xin-Yu Li, Shi-Bao Wang, Cheng-Long Wang, Hao Qin, Yanwen Guo, W. Tian, G. Su, S. Qiu (2022). Fluoride-salt-cooled high-temperature reactors: Review of historical milestones, research status, challenges, and outlook. Renewable & Sustainable Energy Reviews.DOI
164. Xinyu Li, Dalin Zhang, Shi-Chang Yun, Xing-Guang Zhou, Dianqiang Jiang, Xindi Lv, Zhenyu Feng, Wenqiang Wu, W. Tian, S. Qiu, G. Su, Quan-Bin Zhao, Xiuting Liu (2022). Design and Optimal Thermal Efficiency Analysis on Closed Brayton Cycle System of Fluoride-Salt-Cooled High-Temperature Advanced Reactor (Fustar). Social Science Research Network.DOI
165. 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
166. 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》.
167. 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》.
168. 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》.
169. 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》.
170. 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》.
171. 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》.
172. 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》.
173. 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》.
174. 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》.
175. 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
176. 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》.
177. 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》.
178. 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》.
179. Yu-Liang Fang, Hao Qin, Cheng-Long Wang, Lei Zhou, Jing Zhang, Dalin Zhang, W. Tian, G. Su, S. Qiu (2021). Numerical investigation on thermohydraulic performance of high temperature hydrogen in twisted rod channels.DOI
180. Yan Zhang, Dalin Zhang, Cheng-Long Wang, Zhike Lan, W. Tian, G. Su, S. Qiu (2021). Oxygen transport analysis in lead-bismuth eutectic coolant for solid-phase oxygen control.DOI
181. Cheng-Long Wang, Di Wu, Minyang Gui, R. Cai, Dahuan Zhu, Dalin Zhang, W. Tian, S. Qiu, G. Su (2021). Flow blockage analysis for fuel assembly in a lead-based fast reactor.DOI
182. Cheng-Long Wang, Panxiao Li, Dalin Zhang, W. Tian, S. Qiu, Guang-Hui 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
183. Shi-Bao Wang, K. Mikityuk, Petrovic Dorde, Dalin Zhang, G. Su, S. Qiu, W. Tian (2021). Validation of TRACE capability to simulate unprotected transients in Sodium Fast Reactor using FFTF LOFWST Test #13.DOI
184. Yin Zhang, K. Guo, Cheng-Long Wang, Si-Miao Tang, Dalin Zhang, W. Tian, G. Su, S. Qiu (2021). Numerical analysis of segmented thermoelectric generators applied in the heat pipe cooled nuclear reactor. Applied Thermal Engineering.DOI
185. Lin-Yi Yang, Cheng-Long Wang, Hao Qin, Dalin Zhang, W. Tian, G. Su, S. Qiu (2021). Operation performance analysis of a liquid metal droplet radiator for space nuclear reactor.DOI
186. Si-Miao Tang, Xiao Liu, Cheng-Long Wang, Dalin Zhang, G. Su, W. Tian, S. Qiu (2021). Thermal-electrical coupling characteristic analysis of the heat pipe cooled reactor with static thermoelectric conversion. Annals of Nuclear Energy.DOI
187. Yong-Quan Li, Ping Song, T. Feng, Mingjun Wang, Dalin Zhang, W. Tian, S. Qiu (2021). Numerical study on improved design of passive residual heat removal system for China pressurizer reactor.DOI
188. Y. Liang, Mingjun Wang, Zhen Li, Hao-Yu Liao, Dalin Zhang, W. Tian, S. Qiu, Geng-Hui Su (2021). Low temperature overpressurization analysis for CPR1000. International Journal of Advanced Nuclear Reactor Design and Technology.DOI
189. Shi-Jie Cui, Yueheng Lang, Qiang Lian, Xinyu Jiang, Dalin Zhang, W. Tian, G. Su, Xiang Gao, Jian-Gang Li, Qing Zang, Y. Jie, Y. Wan (2021). Preliminary thermal-hydraulic influence of the poloidal nonuniform neutron wall loading on the CFETR HCCB blanket.DOI
190. Yupeng Yang, Yong Li, Cheng-Long Wang, Tao Wang, Zhike Lan, Dalin Zhang, S. Qiu, Geng-Hui Su, W. Tian (2021). Parametric sensitivity analysis of liquid metal helical coil once-through tube steam generator. Nuclear Engineering and Design.DOI
191. Youchun Chen, Dalin Zhang, Rongshuan Xu, Xin Min, Shi-Bao Wang, Bo Wang, Cheng-Long Wang, W. Tian, S. Qiu, G. Su (2021). Start-up characteristics for the test facility of a prototype sodium heated OTSG. Nuclear Engineering and Design.DOI
192. Cheng-Long Wang, Xiao Liu, Minghao Liu, Si-Miao Tang, Zhixing Tian, Dalin Zhang, W. Tian, S. Qiu, G. Su (2021). Experimental study on heat transfer limit of high temperature potassium heat pipe for advanced reactors.DOI
193. Shi-Bao Wang, Dalin Zhang, Yu Liang, Xin'an Wang, S. Qiu, G. Su, W. 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
194. Cheng-Long Wang, Yan Zhang, Dalin Zhang, Zhike Lan, W. Tian, G. Su, S. Qiu (2021). Numerical study of oxygen transport characteristics in lead-bismuth eutectic for gas-phase oxygen control. Nuclear Engineering and Technology.DOI
195. Zhiwen Dai, Cheng-Long Wang, Dalin Zhang, W. Tian, S. Qiu, G. 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
196. Wen-Wen Zhang, Kai-Chao Sun, Cheng-Long Wang, Dalin Zhang, W. Tian, S. Qiu, G. 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
197. Xiao-Rui Yang, Peng-Lei Zhang, Yue Li, Dalin Zhang (2021). A practical design method for two-phase thermosyphon loop based on approaching degree to “ideal cycle”.DOI
198. Cheng-Long Wang, Ran Zhang, K. Guo, Dalin Zhang, W. Tian, S. Qiu, G. Su (2021). Dynamic simulation of a space gas-cooled reactor power system with a closed Brayton cycle. Frontiers in Energy.DOI
199. Zhi-Peng Liu, Cheng-Long Wang, Dalin Zhang, W. Tian, S. Qiu, Geng-Hui Su (2021). Thermal-hydraulic analysis of a lead–bismuth small modular reactor under moving conditions.DOI
200. Shi-Jie Cui, Yueheng Lang, Qiang Lian, Hao-Yu Wan, Dalin Zhang, W. Tian, G. Su, Xiang Gao, Y. Wan (2021). Neurtonics/Thermal-hydraulic analyses of the CFETR HCCB blanket for multiple operation modes under the poloidal nonuniform neutron wall loading condition. Fusion engineering and design.DOI
201. Si-Miao Tang, Cheng-Long Wang, Dalin Zhang, W. Tian, G. Su, S. Qiu (2021). Thermoelectric performance study on a heat pipe thermoelectric generator for micro nuclear reactor application. International Journal of Energy Research.DOI
202. Xi Wang, Dalin Zhang, Mingjun Wang, Yandong Hou, W. Tian, S. Qiu, G. Su (2021). Numerical investigation for the heat transfer mechanisms between subchannels of bar rod bundles cooled by liquid sodium.DOI
203. X.-A. Wang, Dalin Zhang, Mingjun Wang, Yapeng Liu, Lei Zhou, Shi-Bao Wang, Yu Liang, W. Tian, S. Qiu, Geng-Hui Su (2021). Generating Hexahedral Mesh for Wire-wrapped Fuel Assembly With RBF Mesh Deformation Method. Frontiers in Energy Research.DOI
204. Zhixing Tian, Cheng-Long Wang, Jin-Lu Huang, K. Guo, Dalin Zhang, Xiao Liu, G. Su, W. Tian, S. Qiu (2021). Code development and analysis on the operation of liquid metal high temperature heat pipes under full condition.DOI
205. Jun Zhang, Cheng-Long Wang, Jing Zhang, Dalin Zhang, W. Tian, S. Qiu, G. Su (2021). Design research for the porous hexagonal prism shaped fuel element adopted in nuclear thermal propulsion reactor based on neutronics and thermal-hydraulics coupled method.DOI
206. Yonglin Li, Dalin Zhang, D.-C. Sun, Y. Zan, Z. Xi, Wen-Bin Zhuo, P.-Z. Li (2021). Experimental investigation on steam contact condensation in emergency makeup tank. Nuclear Engineering and Design.DOI
207. Zhixing Tian, Xiao Liu, Cheng-Long Wang, Dalin Zhang, W. Tian, S. Qiu, G. Su (2021). Experimental investigation on the heat transfer performance of high-temperature potassium heat pipe for nuclear reactor. Nuclear Engineering and Design.DOI
208. Ping Song, Tang Feng, Dalin Zhang, Lie Chen, Shao-Dan Li, Yuan Lin, S. Qiu (2021). Numerical Analysis on the Thermal-Hydraulic Characteristics for the Reactor Main Vessel Cooling System of Chinese Sodium Cooled Fast Reactor.DOI
209. Qi-Fan Yu, Yan Zhang, Cheng-Long Wang, Chao Guo, Jian Deng, Dalin Zhang, W. Tian, S. Qiu, Geng-Hui Su (2021). Numerical simulation of bubble transport during steam generator tube rupture accident of Lead-cooled Fast Reactor.DOI
210. Yu Liang, Yu-Tong Chen, Dalin Zhang, Xiao Liu, Jian Deng, Cheng-Long Wang, W. Tian, S. Qiu, Geng-Hui Su (2021). Experimental and numerical investigation on flow characteristics of inter-wrapper channel in LMFBR.DOI
211. Zhi-Peng Liu, Dai-Shun Huang, Cheng-Long Wang, Qi-Fan Yu, Dalin Zhang, W. Tian, S. Qiu, G. Su (2021). Flow and heat transfer analysis of lead–bismuth eutectic flowing in a tube under rolling conditions.DOI
212. Chen Wang, Cheng-Long Wang, Yan Zhang, Dalin Zhang, W. Tian, G. Su, S. Qiu (2021). Flow and heat transfer evaluation of lead-bismuth eutectic coolant for nuclear power application. Nuclear Engineering and Design.DOI
213. Lei Zhou, Dalin Zhang, Shi-Bao Wang, Yapeng Liu, Cheng-Long Wang, W. Tian, S. Qiu, Geng-Hui Su (2021). Phenomena identification and ranking table of station blackout accidents for China sodium cooled fast reactor. Annals of Nuclear Energy.DOI
214. Guang-Ya Zhu, T. Wen, Dalin Zhang (2021). Machine learning based approach for the prediction of flow boiling/condensation heat transfer performance in mini channels with serrated fins.DOI
215. Dalin Zhang, Jian Deng, Zhan-Jie Xu, M. Mori (2021). Editorial: Thermal Hydraulics and Safety Analysis in Generation-IV Reactors. Frontiers in Energy Research.DOI
216. Zhiwen Dai, Cheng-Long Wang, Dalin Zhang, W. Tian, S. Qiu, Guang-Hui Su (2021). Impact of axial power distribution on thermal-hydraulic characteristics for thermionic reactor. Nuclear Engineering and Technology.DOI
217. Ze Zhang, Xiao-Ming Chai, Cheng-Long Wang, Hao-Nan Sun, Dalin Zhang, W. Tian, S. Qiu, G. Su (2021). Numerical investigation on startup characteristics of high temperature heat pipe for nuclear reactor. Nuclear Engineering and Design.DOI
218. Yu-Tong Chen, Yu Liang, Dalin Zhang, Shi-Bao Wang, Cheng-Long Wang, Jian Deng, W. Tian, S. Qiu, Geng-Hui Su (2021). A porous medium model for simulating conjugate heat transfer between wire-wrapped fuel bundles under forced and mixed convection.DOI
219. Yu-Tong Chen, Dalin Zhang, Y. Liang, Shi-Bao Wang, Qi-Fan Yu, Cheng-Long Wang, W. Tian, S. Qiu, G. Su (2021). Preliminary development and validation of ACENA code for heavy liquid metal-gas two phase flow simulation.DOI
220. 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
221. 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》.
222. 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》.
223. 王莹杰，王明军，鞠浩然，张大林，田文喜，秋穗正，苏光辉（2020）. 先进压水堆带定位格架5×5燃料棒束通道热工水力特性CFD数值模拟. 《核动力工程》.DOI
224. Shi-Jie Cui, Yueheng Lang, Dalin Zhang, Xinyu Jiang, Hao-Yu Wan, W. Tian, G. Su, Xiang Gao (2020). Three-dimensional validation and analyses of the optimized CFETR HCCB blanket.DOI
225. Limin Liu, Jian Deng, Dalin Zhang, Han-Yang Gu (2020). Review of the experimental research on the thermal‐hydraulic characteristics in the pebble bed nuclear reactor core and fusion breeder blankets. International Journal of Energy Research.DOI
226. Hao-Nan Sun, Si-Miao Tang, Cheng-Long Wang, Jing Zhang, Dalin Zhang, W. Tian, S. Qiu, G. Su (2020). Numerical simulation of a small high-temperature heat pipe cooled reactor with CFD methodology.DOI
227. Shi-Jie Cui, Dalin Zhang, Yueheng Lang, Xinyu Jiang, W. Tian, G. Su, Qi-Xiang Cao, Xing-Hua Wu, Fengchao Zhao, Jian-Gang Li (2020). Preliminary design and analyses of the helium cooled ceramic breeder blanket for CFETR phase II. International Journal of Energy Research.DOI
228. Shi-Jie Cui, Dalin Zhang, Yueheng Lang, Xinyu Jiang, W. Tian, G. Su, Qi-Xiang Cao, Xing-Hua Wu, Fengchao Zhao, Jian-Gang Li (2020). A new method for improving the tritium breeding and releasing performance of China Fusion Engineering Test Reactor phase II helium‐cooled ceramic breeder blanket. International Journal of Energy Research.DOI
229. Jian-Cheng Zhou, Tianzhou Ye, Dalin Zhang, G. Song, Rulei Sun, Jian Deng, W. Tian, G. Su, S. Qiu (2020). Experimental study on vertically upward steam-water two-phase flow patterns in narrow rectangular channel. Nuclear Engineering and Technology.DOI
230. Cheng-Long Wang, Qianni Duan, Minghao Liu, Dalin Zhang, S. Qiu, G. Su, W. Tian (2020). Code development and analysis of heat pipe cooled passive residual heat removal system of Molten salt reactor.DOI
231. Yu Liang, Dalin Zhang, Yu-Tong Chen, Kui Zhang, W. Tian, S. Qiu, G. Su (2020). An experiment study of pressure drop and flow distribution in subchannels of a 37-pin wire-wrapped rod bundle. Applied Thermal Engineering.DOI
232. Limin Liu, P. Peterson, Dalin Zhang, I. Johnson, S. Qiu, G. Su (2020). Scaling and distortion analysis using a simple natural circulation loop for FHR development.DOI
233. Limin Liu, Jian Deng, Dalin Zhang, Cheng-Long Wang, S. Qiu, G. Su (2020). Experimental analysis of flow and convective heat transfer in the water-cooled packed pebble bed nuclear reactor core.DOI
234. Si-Min Luo, Ya-Pei Zhang, Dalin Zhang, G. Su, S. Qiu (2020). Convection of internal-heated two-layer fluids with deformable interface under swinging motion conditions.DOI
235. Lian-Fang Hu, K. Ge, Ya-Pei Zhang, Dalin Zhang, G. Su, W. Tian, S. Qiu (2020). Experimental research on fragmentation characteristics of molten stainless steel discharged into sodium pool and comparison with molten copper.DOI
236. G. Song, Rulei Sun, Dalin Zhang, G. Su, W. Tian, S. Qiu (2020). Experimental study on flow characteristics of rectangular narrow channel. International Journal of Advanced Nuclear Reactor Design and Technology.DOI
237. Zhiwen Dai, Cheng-Long Wang, Dalin Zhang, W. Tian, S. Qiu, Geng-Hui Su (2020). Design and analysis of a free-piston stirling engine for space nuclear power reactor. Nuclear Engineering and Technology.DOI
238. Wen-Wen Zhang, Dalin Zhang, Cheng-Long Wang, W. Tian, S. Qiu, G. Su (2020). Conceptual design and analysis of a megawatt power level heat pipe cooled space reactor power system.DOI
239. Ying-Jie Wang, Mingjun Wang, Haoran Ju, Min-Fu Zhao, Dalin Zhang, W. Tian, Tian-Cai Liu, S. Qiu, G. Su (2020). CFD simulation of flow and heat transfer characteristics in a 5×5 fuel rod bundles with spacer grids of advanced PWR. Nuclear Engineering and Technology.DOI
240. Ran Zhang, Yu Liang, Xiao Liu, Cheng-Long Wang, Dalin Zhang, S. Qiu, G. Su (2020). Thermal-hydraulic analysis of pellet bed reactor for space nuclear electric propulsion.DOI
241. Lianfa Wang, Jian Deng, Mingjun Wang, Dalin Zhang, S. Qiu, G. Su, W. Tian (2020). Numerical simulation of temperature heterogeneity inside the AP1000 upper plenum and hot leg.DOI
242. Hao Qin, Cheng-Long Wang, Dalin Zhang, W. Tian, G. Su, S. Qiu (2020). Parametric investigation of radiation heat transfer and evaporation characteristics of a liquid droplet radiator.DOI
243. G. Song, Dalin Zhang, Geng-Hui Su, Guo Chen, W. Tian, S. Qiu (2020). Assessment of ECCMIX component in RELAP5 based on ECCS experiment.DOI
244. G. Song, Yu Liang, Rulei Sun, Dalin Zhang, Jian Deng, G. Su, W. Tian, S. Qiu (2020). A dryout mechanism model for rectangular narrow channels at high pressure conditions.DOI
245. Cheng-Long Wang, Minghao Liu, Dalin Zhang, S. Qiu, G. Su, W. Tian (2020). Experimental study on transient performance of heat pipe-cooled passive residual heat removal system of a molten salt reactor. Progress in nuclear energy (New series).DOI
246. Mingjun Wang, Jing Chen, Dalin Zhang, Jing Zhang, W. Tian, G. Su, S. Qiu (2020). Numerical study on the thermal stratification characteristics in the upper plenum of sodium-cooled fast reactor (SFR). Annals of Nuclear Energy.DOI
247. Cheng Zhang, Haoran Ju, Dalin Zhang, Shu-Xian Wu, Yi-Jun Xu, Ying-Wei Wu, S. Qiu, G. Su (2020). PIV measurement and numerical investigation on flow characteristics of simulated fast reactor fuel subassembly.DOI
248. Wen-Wen Zhang, Dalin Zhang, Xiao Liu, W. Tian, S. Qiu, G. Su (2020). Thermal-hydraulic analysis of the thermoelectric space reactor power system with a potassium heat pipe radiator.DOI
249. G. Song, Yu Liang, Rulei Sun, Dalin Zhang, Jian Deng, G. Su, W. Tian, S. Qiu (2020). A critical heat flux model for unilateral heating rectangular narrow channel.DOI
250. G. Song, Dalin Zhang, Qiang Liu, Y. Xiang, Gui-Hua Su, W. Tian, S. Qiu (2020). RELAP5/MOD3.4 calculation and model evaluation based on upper plenum entrainment experiment in AP1000.DOI
251. Shi-Bao Wang, Dalin Zhang, Yapeng Liu, Cheng-Long Wang, S. Qiu, G. Su, W. 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
252. Xin-Yu Li, Jie Cheng, Dalin Zhang, Zhiwen Dai (2020). Design and optimization of passive residual heat removal system for lead‐bismuth reactor SVBR‐100. International Journal of Energy Research.DOI
253. Zhiwen Dai, Cheng-Long Wang, Dalin Zhang, W. Tian, S. Qiu, G. Su (2020). Numerical simulation on thermal‐hydraulic and thermoelectric characteristics of the TOPAZ‐II reactor core. International Journal of Energy Research.DOI
254. Ran Zhang, K. Guo, Cheng-Long Wang, Dalin Zhang, W. Tian, S. Qiu, G. 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
255. Yan Zhang, Cheng-Long Wang, R. Cai, Zhike Lan, Ya-Ou Shen, Dalin Zhang, W. Tian, G. Su, S. Qiu (2020). Experimental investigation on flow and heat transfer characteristics of lead–bismuth eutectic in circular tubes. Applied Thermal Engineering.DOI
256. Di Wu, Cheng-Long Wang, Minyang Gui, Zhike Lan, Qi Lu, Dalin Zhang, W. Tian, S. Qiu, G. 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
257. Cheng-Long Wang, Hao Qin, Dalin Zhang, W. Tian, G. Su, S. 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
258. Rulei Sun, G. Song, Dalin Zhang, Jian Deng, G. Su, F. A. Kulacki, W. Tian, S. Qiu (2020). Experimental study of single-phase flow and heat transfer in rectangular channels under uniform and non-uniform heating.DOI
259. G. Song, Di Wu, Rulei Sun, Yu Liang, Dalin Zhang, Jian Deng, G. Su, W. Tian, S. Qiu (2020). Theoretical study of steady-state characteristics of natural circulation system.DOI
260. Jing Zhang, Chen-Xi Li, Jian Deng, Hao-Nan Sun, Ying-Wei Wu, Mingjun Wang, Dalin Zhang, W. Tian, S. Qiu, G. Su (2020). Experimental and theoretical study on fluid-structure interaction and non-equilibrium of the flow through micro cracks. Annals of Nuclear Energy.DOI
261. Q. Lu, Qi Zhang, Dalin Zhang, Zhihan Lv (2020). Numerical Investigation on the Dynamic Characteristics of an Adjustable Power Turbine Used in Environmental Control System. Complex.DOI
262. Shi-Bao Wang, Dalin Zhang, S. Qiu, G. Su, W. 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
263. Cheng-Long Wang, Yupeng Yang, Minghao Liu, Dalin Zhang, S. Qiu, Geng-Hui Su, W. 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
264. Xi Wang, Dalin Zhang, Mingjun Wang, Ping Song, Shi-Bao Wang, Y. Liang, Ya-Pei Zhang, W. Tian, S. Qiu, G. Su (2020). Hybrid medium model for conjugate heat transfer modeling in the core of sodium-cooled fast reactor.DOI
265. K. Guo, Cheng-Long Wang, Dalin Zhang, W. Tian, G. Su, S. Qiu (2020). Investigations of near-wall bubble behavior in wire heaters pool boiling.DOI
266. Rulei Sun, G. Song, Dalin Zhang, G. Su, F. A. Kulacki, W. Tian (2020). Flow Boiling Pressure Drop Characteristics in Rectangular Channels under Uniform and Non-Uniform Heating.DOI
267. Dalin Zhang, Rongshuan Xu, Youchun Chen, Bo Wang, Cheng-Long Wang, W. Tian, S. Qiu, G. 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
268. Rongshuan Xu, Ping Song, Dalin Zhang, W. Tian, S. Qiu, G. Su (2020). Numerical analysis on flow instability of parallel channels in steam generator for sodium‐cooled fast reactor. International Journal of Energy Research.DOI
269. Yapeng Liu, Dalin Zhang, Ping Song, Shi-Bao Wang, Yu Liang, Lei Zhou, Cheng-Long Wang, Mingjun Wang, W. Tian, S. Qiu, Geng-Hui Su (2020). Analysis of the natural circulation test of PHENIX reactor by the THACS code.DOI
270. 刘伟，张勇，蒋孝蔚，张诚，张大林（2019）. 板型燃料元件反应堆瞬态热工水力分析程序的开发与验证. 《核动力工程》.DOI
271. 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》.
272. 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》.
273. Peng-Lei Zhang, Xiao-Rui Yang, Xing Rong, Dalin Zhang (2019). Simulation on the thermal performance of two-phase thermosyphon loop with large height difference.DOI
274. Lie Chen, W. Tian, Rong-Hua Chen, Dalin Zhang, G. Su, S. Qiu, Meng-Meng Xi, Du Shu (2019). Development and application of SANPR with coupling numerical methods for analysis of effect of moving condition on natural circulation of nuclear power system. Nuclear Engineering and Design.DOI
275. Si-Min Luo, Ya-Pei Zhang, Dalin Zhang, G. Su, S. Qiu (2019). Numerical analysis of simulant effect on natural convection characteristics in corium pools. Applied Thermal Engineering.DOI
276. T. Wen, Hong-Bo Zhan, Dalin Zhang (2019). Flow condensation heat transfer characteristics of R134a in multiport mini-channel by jet impingement cooling. Applied Thermal Engineering.DOI
277. Zhiwen Dai, Cheng-Long Wang, Dalin Zhang, W. Tian, S. Qiu, G. Su (2019). Thermoelectric characteristics analysis of thermionic space nuclear power reactor. International Journal of Energy Research.DOI
278. T. Wen, Hong-Bo Zhan, Dalin Zhang (2019). Flow boiling heat transfer in mini channel with serrated fins: Experimental investigation and development of new correlation. International Journal of Heat and Mass Transfer.DOI
279. Hao Qin, Cheng-Long Wang, Dalin Zhang, W. Tian, G. Su, S. Qiu (2019). Radiative and evaporative characteristics analysis of a liquid droplet layer for space applications.DOI
280. Zhiwen Dai, Cheng-Long Wang, Xiao Liu, Dalin Zhang, S. Qiu, G. Su (2019). Thermoelectric Characteristics Analysis of TOPAZ-II. Transactions of the American Nuclear Society.DOI
281. Hao Qin, Cheng-Long Wang, Dalin Zhang, W. Tian, S. Qiu, G. Su (2019). Transient analysis of tritium transport characteristics in fluoride-salt-cooled high-temperature reactor. Progress in nuclear energy (New series).DOI
282. Linfeng Li, Dian-Qi Fang, Dalin Zhang, Mingjun Wang, W. Tian, G. Su, S. Qiu (2019). Flow and heat transfer characteristics in plate-type fuel channels after formation of blisters on fuel elements. Annals of Nuclear Energy.DOI
283. Hao Yu, Mingjun Wang, R. Cai, Dalin Zhang, W. Tian, S. Qiu, G. Su (2019). Development and validation of boron diffusion model in nuclear reactor core subchannel analysis. Annals of Nuclear Energy.DOI
284. Jia-Wei Bian, Dalin Zhang, Rulei Sun, Ying-Wei Wu, W. Tian, G. Su, S. Qiu (2019). Experimental study on spray characteristics of pressure-swirl nozzle in China advanced PWR containment. Nuclear Engineering and Design.DOI
285. Jing Zhang, Yichao Ma, Mingjun Wang, Dalin Zhang, S. Qiu, W. Tian, G. Su (2019). Prediction of flow boiling heat transfer coefficient in horizontal channels varying from conventional to small-diameter scales by genetic neural network. Nuclear Engineering and Technology.DOI
286. Hao Qin, Cheng-Long Wang, Mingjun Wang, Dalin Zhang, W. Tian, G. Su, S. Qiu (2019). Numerical investigation on thermal-hydraulic characteristics of NaK in a helical wire wrapped annulus. International Journal of Heat and Mass Transfer.DOI
287. Dalin Zhang, Jiang-Tao Yu, W. Tian, G. Su, S. Qiu (2019). Heat transfer characteristics in super-low finned-tube bundles of moisture separator reheaters. Nuclear Engineering and Design.DOI
288. Rongshuan Xu, Dalin Zhang, W. Tian, S. Qiu, G. Su (2019). Thermal-hydraulic analysis code development for sodium heated once-through steam generator. Annals of Nuclear Energy.DOI
289. Si-Min Luo, Ya-Pei Zhang, Dalin Zhang, G. Su, S. Qiu (2019). SIMULATIONS ON NATURAL CONVECTION OF STRATIFIED MELT POOLS WITH VOLUMETRIC HEAT GENERATION. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
290. Rongshuan Xu, Dalin Zhang, W. Tian, S. Qiu, G. Su (2019). Development of thermal hydraulic design code for SFR steam generators. Nuclear Engineering and Design.DOI
291. Xiao-Yan Wang, W. Tian, Siyang Huang, Rong-Hua Chen, Dalin Zhang, S. Qiu, G. Su (2019). Theoretical investigation of two-phase flow instability between parallel channels of natural circulation in rolling motion. Nuclear Engineering and Design.DOI
292. Ping Song, Dalin Zhang, T. Feng, Shi-Bao Wang, Jing Chen, Xin'an Wang, X. Xue, Ya-Pei Zhang, Mingjun Wang, S. Qiu, Geng-Hui Su (2019). Numerical approach to study the thermal-hydraulic characteristics of Reactor Vessel Cooling system in sodium-cooled fast reactors. Progress in nuclear energy (New series).DOI
293. Yangbin Deng, Ying-Wei Wu, Dalin Zhang, W. Tian, G. Su, S. Qiu (2019). Simulation on Pellet–Cladding Mechanical Interaction of Accident Tolerant Fuel With Coated Cladding. Journal of Nuclear Engineering and Radiation Science.DOI
294. Dalin Zhang, Shi-Bao Wang, S. Qiu, G. Su (2019). Numerical Study on the Thermal Stratification Phenomenon in the Sodium-Cooled Fast Reactor.
295. 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》.
296. 靖剑平，吴林，夏雨齐，毕金生，贾斌，张大林（2018）. 10 MWt固态燃料熔盐堆内流动和换热特性研究. 《核科学与工程》.
297. 郑美银，陈平，李权，张大林，田文喜，苏光辉（2018）. 钠冷行波堆和驻波堆堆芯特性对比分析. 《原子能科学技术》.
298. 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》.
299. 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》.
300. Si-Min Luo, Xin'an Wang, Ya-Pei Zhang, Dalin Zhang, S. Qiu, G. Su (2018). Numerical Research on Melt Pool Flow Characteristics Under Rolling Condition. Volume 9: Student Paper Competition.DOI
301. Jiang-Tao Yu, Dalin Zhang, Lei-Tai Shi, Zhi-Wei Wang, W. Tian, G. Su, S. 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
302. Jiang-Tao Yu, Dalin Zhang, Lei-Tai Shi, W. Tian, Geng-Hui Su, S. 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
303. Dalin Zhang, Limin Liu, Minghao Liu, Rongshuan Xu, C. Gong, Jun Zhang, Cheng-Long Wang, S. Qiu, G. Su (2018). Review of conceptual design and fundamental research of molten salt reactors in China.DOI
304. Shi-Jie Cui, Dalin Zhang, W. Tian, G. Su, S. Qiu (2018). Numerical research on the coupling optimization design rule of the CFETR HCSB blanket using the NTCOC code.DOI
305. Shi-Bao Wang, Dalin Zhang, Cheng-Long Wang, Ping Song, Jing Chen, S. Qiu, G. Su (2018). Validation of a Code and Effect of Turbulence Model on Predicting Thermal Stratification Phenomena in the Upper Plenum of SFR. Volume 9: Student Paper Competition.DOI
306. T. Wen, Hong-Bo Zhan, Lin Lu, Dalin Zhang (2018). Experimental investigation and development of new correlation for flow boiling heat transfer in mini-channel. International journal of thermal sciences.DOI
307. Minghao Liu, Dalin Zhang, Cheng-Long Wang, S. Qiu, G. Su, W. 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
308. Jia-Wei Bian, Dalin Zhang, Rulei Sun, Ying-Wei Wu, W. Tian, G. Su, S. Qiu (2018). Experimental Study on Spray Pattern of Pressure-Swirl Nozzle in Reactor Containment. Volume 9: Student Paper Competition.DOI
309. Shi-Jie Cui, Dalin Zhang, W. Tian, G. Su, S. Qiu (2018). Conceptual Design and Neutronics/Thermal-Hydraulic Coupling Optimization Analyses of Two Typical Helium Cooled Solid Breeder Blanket Modules for CFETR Phase II. Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues.DOI
310. T. Wen, Hong-Bo Zhan, Yimo Luo, Dalin Zhang (2018). Experimental Study on the Flow Boiling Heat Transfer Characteristics in a Mini-Channel with Offset Fins. Proceedings.DOI
311. Rulei Sun, Yichen Yang, Dalin Zhang, Jia-Wei Bian, S. Qiu, G. Su (2018). Study on Thermal-Hydraulic Characteristics of Vertical Narrow Rectangular Channel With Large Aspect Ratio Under Transverse Uneven Heating. Volume 9: Student Paper Competition.DOI
312. Shi-Jie Cui, Dalin Zhang, Xinli Gao, W. Tian, G. Su, S. Qiu (2018). Conceptual design and comprehensive optimization analysis of a fusion-fission hybrid reactor water-cooled pressure tube blanket.DOI
313. Rulei Sun, Dalin Zhang, Yu Liang, Mingjun Wang, W. Tian, S. Qiu, G. Su (2018). Development of a subchannel analysis code for SFR wire-wrapped fuel assemblies.DOI
314. Dalin Zhang, Shi-Jie Cui, Jie Cheng, W. Tian, G. Su (2018). Improving the optimization algorithm of NTCOC for application in the HCSB blanket for CFETR Phase II. Fusion engineering and design.DOI
315. Cheng-Long Wang, Kai-Chao Sun, Dalin Zhang, W. Tian, S. Qiu, G. Su (2018). Thermal‐hydraulic design and analysis of a small modular molten salt reactor (MSR) with solid fuel.DOI
316. Jing Chen, Dalin Zhang, Ping Song, Xin'an Wang, Shi-Bao Wang, Yu Liang, S. Qiu, Ya-Pei Zhang, Mingjun Wang, G. Su (2018). CFD investigation on thermal-hydraulic behaviors of a wire-wrapped fuel subassembly for sodium-cooled fast reactor.DOI
317. Hao Qin, Cheng-Long Wang, S. Qiu, Dalin Zhang, W. Tian, G. Su (2018). Study of tritium transport characteristics in a transportable fluoride‐salt‐cooled high‐temperature reactor.DOI
318. T. Wen, Hong-Bo Zhan, Dalin Zhang (2018). Flow condensation in a mini channel with serrated fins with jet impingement cooling: Experimental study and development of new correlation. International Journal of Heat and Mass Transfer.DOI
319. Shi-Bao Wang, Dalin Zhang, Ping Song, Ya-Pei Zhang, Mingjun Wang, Ying-Wei Wu, S. Qiu (2018). Validation of a methodology for thermal stratification analysis in sodium‐cooled fast reactors. International Journal of Energy Research.DOI
320. Limin Liu, Dalin Zhang, Jian Song, Cheng-Long Wang, Xinli Gao, W. Tian, S. Qiu, G. Su (2018). Modification and application of Relap5 Mod3 code to several types of nonwater‐cooled advanced nuclear reactors.DOI
321. Ping Song, Dalin Zhang, T. Feng, Shi-Bao Wang, Ya-Pei Zhang, Mingjun Wang, S. Qiu, G. Su (2018). Development and Basic Verification of Decay Heat Removal Analysis Code of Sodium-Cooled Fast Reactor. Volume 6A: Thermal-Hydraulics and Safety Analyses.DOI
322. Mingjun Wang, Y. Xiang, Shi-Jie Cui, Di Liu, W. Tian, Dalin Zhang, S. Qiu, G. Su (2018). Numerical study on the purge gas flow and heat transfer characteristics in helium cooled solid breeder blanket of CFETR.DOI
323. Jing Chen, Dalin Zhang, S. Qiu, Kui Zhang, Mingjun Wang, G. Su (2018). CFD Investigation of Thermal-Hydraulic Behaviors in Full Reactor Core for Sodium-Cooled Fast Reactor. Volume 9: Student Paper Competition.DOI
324. Limin Liu, Dalin Zhang, Linfeng Li, Yichen Yang, Cheng-Long Wang, S. Qiu, Geng-Hui 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
325. Yong-Zheng Chen, Ying-Wei Wu, Mingjun Wang, Y.-P. Zhang, Bing Tan, Dalin Zhang, W. Tian, S. Qiu, G. Su (2018). Development of a multi-compartment containment code for advanced PWR plant. Nuclear Engineering and Design.DOI
326. Nina Yue, Dalin Zhang, Jing Chen, Ping Song, Xin'an Wang, Shi-Bao Wang, S. Qiu, Geng-Hui Su, Ya-Pei Zhang (2018). The development and validation of the inter-wrapper flow model in sodium-cooled fast reactors. Progress in nuclear energy (New series).DOI
327. Limin Liu, Dalin Zhang, Linfeng Li, Yichen Yang, Cheng-Long Wang, S. Qiu (2018). Experimental Studies on the Thermal-Hydraulics of Dowtherm A Through the Pebble Bed With Internal Heat Generation. Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues.DOI
328. Minghao Liu, Dalin Zhang, Cheng-Long Wang, S. Qiu, G. Su, W. Tian (2018). Experimental study on the heat transfer characteristics of fluoride salt in the new conceptual passive heat removal system of molten salt reactor.DOI
329. Hao Qin, Cheng-Long Wang, S. Qiu, Dalin Zhang, W. Tian, G. Su (2018). Tritium Transport Characteristics Analysis in Molten Salt Reactor Under Transient Conditions. Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation.DOI
330. Nina Yue, R. Cai, Yun Wang, S. Qiu, Dalin Zhang (2018). The Choose of Decay Heat Removal Systems of SFR. Volume 6A: Thermal-Hydraulics and Safety Analyses.DOI
331. Zheng-Hui Ma, Rong-Hua Chen, Maolin Tian, Jian Song, Dalin Zhang, G. Su, Xiaorong Li, Ling-Lan Zhou, S. Qiu (2018). Analysis of flow blockage accidents in rectangular fuel assembly based on CFD methodology.DOI
332. Cheng-Long Wang, Hao Qin, Dalin Zhang, W. Tian, S. Qiu, G. Su (2018). Numerical study of tritium transport characteristics in Thorium Molten Salt Reactor with Solid Fuel (TMSR-SF).DOI
333. Yangbin Deng, Ying-Wei Wu, C. Gong, Dalin Zhang, W. Tian, S. Qiu, G. Su (2018). Upgrade of FROBA code and its application in thermal-mechanical analysis of space reactor fuel. Nuclear Engineering and Design.DOI
334. 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
335. 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》.
336. 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》.
337. 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》.
338. 靖剑平，贾斌，雷蕾，毕金生，左嘉旭，刘雅宁，张春明，张大林（2017）. 不同燃料球排布方式下熔盐堆堆芯流动和换热特性研究. 《核技术》.
339. Cheng-Long Wang, Limin Liu, Minghao Liu, Dalin Zhang, W. Tian, S. Qiu, G. Su (2017). Conceptual design and analysis of heat pipe cooled silo cooling system for the transportable fluoride-salt-cooled high-temperature reactor.DOI
340. T. Feng, Dalin Zhang, Ping Song, W. Tian, Wei Li, G. Su, S. Qiu (2017). Numerical research on water hammer phenomenon of parallel pump-valve system by coupling FLUENT with RELAP5.DOI
341. Shi-Jie Cui, Dalin Zhang, Jie Cheng, W. Tian, G. Su (2017). Numerical research on the neutronic/thermal-hydraulic/mechanical coupling characteristics of the optimized helium cooled solid breeder blanket for CFETR.DOI
342. Shi-Jie Cui, Dalin Zhang, Jie Cheng, W. Tian, G. Su（2017）. CFETRのための最適化されたヘリウム冷却固体増殖材ブランケットのneutronic/thermal hydraulic/mechanical結合特性に関する数値的研究【Powered by NICT】.
343. Dalin Zhang, Jing Chen, Ping Song, Shi-Bao Wang, Xin'an Wang, Linfeng Li, S. Qiu, G. Su (2017). Theoretical and Experimental Research on the Single-Phase and Incipient Boiling Heat Transfer of Liquid Metal Sodium.DOI
344. Cheng-Long Wang, Jing Chen, S. Qiu, W. Tian, Dalin Zhang, G. Su (2017). Performance analysis of heat pipe radiator unit for space nuclear power reactor.DOI
345. Dalin Zhang, Limin Liu, Minghao Liu, Rongshuan Xu, C. Gong, S. Qiu (2017). Neutronics/Thermal-hydraulics Coupling Analysis for the Liquid-Fuel MOSART Concept.DOI
346. Limin Liu, Dalin Zhang, Qi-Qi Yan, Rongshuan Xu, Cheng-Long Wang, S. Qiu, G. Su (2017). RELAP5 MOD3.2 modification and application to the transient analysis of a fluoride-salt-cooled high-temperature reactor.DOI
347. Qiang Lian, Shi-Jie Cui, W. Tian, Jing Zhang, Dalin Zhang, G. Su (2017). Preliminary accident analysis of Loss of Off-Site Power and In-Box LOCA for the CFETR helium cooled solid breeder blanket.DOI
348. Cheng-Long Wang, Kai-Chao Sun, Lin-wen Hu, Dalin Zhang, W. Tian, S. Qiu, Geng-Hui Su (2017). Transient Safety Analysis of a Transportable Fluoride-Salt-Cooled High-Temperature Reactor Using RELAP5-3D.DOI
349. Shi-Jie Cui, Dalin Zhang, Jian Ge, Jie Cheng, W. Tian, G. Su, S. 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.DOI
350. Jiang-Tao Yu, Dalin Zhang, Lei-Tai Shi, Zhi-Wei Wang, W. Tian, G. Su, S. Qiu (2017). Experimental Study on the Steam-Water Co-Current Flow Friction Multiplier of the AP1000 Surge Line.DOI
351. Cheng-Long Wang, Kai-Chao Sun, Dalin Zhang, W. Tian, S. Qiu, G. Su (2017). Uncertainty analysis of Transportable Fluoride-salt-cooled High-temperature Reactor (TFHR) using coupled DAKOTA with RELAP-3D method.DOI
352. Yangbin Deng, Ying-Wei Wu, Dalin Zhang, Qing Lu, W. Tian, S. Qiu, Guang-Hui Su（2017）. 金属マトリックス分散板状燃料の熱的‐機械的カップリング挙動解析【Powered by NICT】.
353. Jing Chen, Dalin Zhang, Xin'an Wang, S. Qiu, Geng-Hui Su, Ya-Pei Zhang (2017). CFD Simulation of a 61-pin Wire-wrapped Fuel Subassembly for Sodium Cooled Fast Reactor.
354. Si-Miao Tang, Jian Song, Dalin Zhang, Cheng-Long Wang, S. Qiu, Guang-Hui Su, W. Tian (2017). Thermal-Hydraulic Analysis of the EBR-II SHRT-45R Unprotected Loss of Flow Experiment With Modified RELAP5.DOI
355. Shi-Jie Cui, Dalin Zhang, Qiang Lian, W. Tian, Jie Cheng, G. Su, S. Qiu (2017). Development of a neutronics/thermal-hydraulic coupling optimization code and its application on the CFETR HCSB blanket.DOI
356. Shi-Jie Cui, Dalin Zhang, Qiang Lian, Jie Cheng, W. Tian, G. Su, S. Qiu (2017). Evaluation and optimization of tritium breeding, shielding and nuclear heating performances of the helium cooled solid breeder blanket for CFETR.DOI
357. Jian Ge, Dalin Zhang, W. Tian, S. Qiu, G. Su (2017). Coupled Analysis of Thermal Hydraulics and Neutronics for a Molten Salt Reactor.DOI
358. Yangbin Deng, Ying-Wei Wu, Dalin Zhang, Qing Lu, W. Tian, S. Qiu, G. Su (2017). Thermal-mechanical coupling behavior analysis on metal-matrix dispersed plate-type fuel.DOI
359. Yangbin Deng, Ying-Wei Wu, Bowen Qiu, Dalin Zhang, Mingjun Wang, W. Tian, S. Qiu, G. Su (2017). Development of a new Pellet-Clad Mechanical Interaction (PCMI) model and its application in ATFs.DOI
360. Yangbin Deng, Bowen Qiu, Ying-Wei Wu, Dalin Zhang, W. Tian, S. Qiu, G. Su (2017). Simulation on Pellet-Cladding Mechanical Interaction (PCMI) of Accident Tolerant Fuel (ATF) With Coated Cladding.DOI
361. 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》.
362. 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》.
363. 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》.
364. Yangbin Deng, Dalin Zhang, Qing Lu, Ying-Wei Wu, W. Tian, S. Qiu, G. Su (2016). Mechanism Study and Numerical Simulation on Blistering of Plate-Type Fuel.DOI
365. S. Qiu, Dalin Zhang, L. Liu, M. Liu, R. Xu, C. Gong, G. Su (2016). Coupled neutronics/thermal-hydraulics and safety characteristics of liquid-fueled Molten Salt Reactors.DOI
366. Shi-Jie Cui, Dalin Zhang, Jie Chang, W. Tian, S. Qiu, G. Su (2016). Thermo-Hydraulic Analysis of the Optimized Helium Cooled Solid Breeder Blanket for CFETR.DOI
367. Limin Liu, Qi-Qi Yan, Dalin Zhang, S. Qiu, G. Su (2016). Investigation of the Modified RELAP5 MOD 3.2 Capability to Simulate the Transients of the Fluoride-Salt High-Temperature Reactors.DOI
368. Mei-yin Zheng, W. Tian, Dalin Zhang, S. Qiu, G. Su (2016). Performance of radial fuel shuffling sodium cooled Breed and Burn reactor core.DOI
369. Wen-Wen Zhang, Dalin Zhang, W. Tian, S. Qiu, G. Su (2016). Thermal-hydraulic analysis of the improved TOPAZ-II power system using a heat pipe radiator.DOI
370. Limin Liu, Dalin Zhang, Qing Lu, Kunpeng Wang, S. Qiu (2016). Preliminary neutronic and thermal-hydraulic analysis of a 2 MW Thorium-based Molten Salt Reactor with Solid Fuel.DOI
371. Jian Ge, Cheng-Long Wang, Yao Xiao, W. Tian, S. Qiu, G. Su, Dalin Zhang, Ying-Wei Wu (2016). Thermal-hydraulic analysis of a fluoride-salt-cooled pebble-bed reactor with CFD methodology.DOI
372. Wen-Wen Zhang, Zai-Yong Ma, Dalin Zhang, W. Tian, S. Qiu, G. Su (2016). Transient thermal–hydraulic analysis of a space thermionic reactor.DOI
373. Yangbin Deng, Ying-Wei Wu, Dalin Zhang, W. Tian, S. Qiu, G. Su (2016). Development of a thermal–mechanical behavior coupling analysis code for a dual-cooled annular fuel element in PWRs.DOI
374. Yangbin Deng, Ying-Wei Wu, Yuan-Ming Li, Dalin Zhang, W. Tian, G. Su, S. Qiu (2016). Mechanism study and theoretical simulation on heat split phenomenon in dual-cooled annular fuel element.DOI
375. Jiang-Tao Yu, Dalin Zhang, Lei-Tai Shi, Zhi-Wei Wang, Shi-Xiang Yan, B. Dong, W. Tian, G. Su, S. Qiu (2016). Experimental Investigation of Air-Water CCFL in the Pressurizer Surge Line of AP1000. Nuclear Technology.DOI
376. 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》.
377. 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》.
378. 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》.
379. 邓阳斌，巫英伟，张伟旭，田文喜，张大林，苏光辉（2015）. 双面冷却环形燃料元件的几何尺寸优化. 《原子能科学技术》.
380. 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》.
381. Dalin Zhang, A. Rineiski, Cheng-Long Wang, Zhangpeng Guo, Yao Xiao, S. Qiu (2015). Development of a kinetic model for safety studies of liquid-fuel reactors.DOI
382. Lin-wen Hu, Cheng-Long Wang, Kai-Chao Sun, Dalin Zhang, S. Qiu (2015). THREE-DIMENSIONAL THERMAL HYDRAULIC ANALYSIS OFA TRANSPORTABLE FLUORIDE-SALT-COOLED HIGH-TEMPERATURE REACTOR.
383. A. Rineiski, B. Vezzoni, Dalin Zhang, M. Marchetti, F. Gabrielli, W. Maschek, X.-N. Chen, L. Buiron, J. Křepel, Kai-Chao Sun, K. Mikityuk, F. Polidoro, D. Rochman, Koning A. J., D. F., Tsige-Tamirat Haileyesus, R. Sunderland (2015). ESFR core optimization and uncertainty studies.
384. Zicheng Qiu, Zheng-Hui Ma, S. Qiu, G. Su, Dalin Zhang, Yun Wu, W. Tian (2015). Experimental research on the thermal hydraulic characteristics of sodium boiling in an annulus.DOI
385. W. Tian, Dalin Zhang, S. Qiu, Jian Ge (2015). FLUENT-based computationfor a time-space-dependent neutron kinetics model.
386. Meng-Meng Xi, Dalin Zhang, Mao Tang, Cheng-Long Wang, Mei-yin Zheng, S. Qiu (2015). Thermal hydraulic investigations and optimization on the EVC system of a PWR by CFD simulation.DOI
387. Mei-yin Zheng, W. Tian, Dalin Zhang, S. Qiu, G. Su (2015). Minor actinide transmutation in a board type sodium cooled breed and burn reactor core.DOI
388. Yao Xiao, Lin-wen Hu, S. Qiu, Dalin Zhang, G. Su, W. Tian (2015). Development of a Thermal-Hydraulic Analysis Code and Transient Analysis for a Fluoride-Salt-Cooled High-Temperature Test Reactor.DOI
389. Limin Liu, Dalin Zhang, Qing Lu, Kunpeng Wang, S. Qiu (2015). 1-s2.0-S0149197015300779-main.
390. Wen-Wen Zhang, W. Tian, S. Qiu, G. Su, Dalin Zhang (2015). ICONE23-1792 DEVELOPMENT OF TRANSIENT THERMAL-HYDRAULIC ANALYSIS CODE FOR THE SPACE THERMIONIC REACTOR.DOI
391. Rui Li, S. Wang, A. Rineiski, Dalin Zhang, E. Merle-Lucotte (2015). Transient analyses for a molten salt fast reactor with optimized core geometry.DOI
392. Jian Ge, Dalin Zhang, W. Tian, Kunpeng Wang, S. Qiu, G. Su (2015). Steady and transient solutions of neutronics problems based on finite volume method (FVM) with a CFD code.DOI
393. Qi-Qi Yan, Rongshuan Xu, Dalin Zhang, S. Qiu, Limin Liu (2015). PRELIMINARY NEUTRONIC ANDTRANSIENT ANALYSIS OF A 20 MW THORIUM-BASED MOLTEN SALT REACTOR WITH SOLID FUEL.
394. 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》.
395. 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》.
396. 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》.
397. Dalin Zhang, Mei-yin Zheng, Hong-Bae An, Xue-Nong Chen, W. Tian, S. Qiu, G. Su (2014). Numerical studies of stepwise radial fuel shuffling in a traveling wave reactor. Science China Technological Sciences.DOI
398. Cheng-Long Wang, Yao Xiao, Jian-Jun Zhou, Dalin Zhang, S. Qiu, W. Tian, G. Su (2014). Thermal Hydraulic Studies of a Fluoride Salt Cooled High Temperature Test Reactor With Different CFD Methods.DOI
399. Wei Li, Xiaoli Wu, Dalin Zhang, G. Su, W. Tian, S. Qiu (2014). Preliminary study of coupling CFD code FLUENT and system code RELAP5.DOI
400. Cheng-Long Wang, Yao Xiao, Jian-Jun Zhou, Dalin Zhang, S. Qiu, G. Su, Xiang-Zhou Cai, Na-Xiu Wang, Wei Guo (2014). Computational Fluid Dynamics Analysis of a Fluoride Salt–Cooled Pebble-Bed Test Reactor.DOI
401. Mei-yin Zheng, W. Tian, Hong-Yang Wei, Dalin Zhang, Ying-Wei Wu, S. Qiu, G. Su (2014). Development of a MCNP–ORIGEN burn-up calculation code system and its accuracy assessment.DOI
402. Mei-yin Zheng, W. Tian, Xiao Chu, Dalin Zhang, S. Qiu, G. Su (2014). Preliminary design study of a board type radial fuel shuffling sodium cooled breed and burn reactor core.DOI
403. Yao Xiao, Lin-wen Hu, S. Qiu, Dalin Zhang, G. Su, W. Tian (2014). Development of a Thermal-Hydraulic Analysis Code and Transient Analysis for a FHTR.DOI
404. Mingjun Wang, Dalin Zhang, S. Qiu, W. Tian, G. Su (2014). Accident analyses for china pressurizer reactor with an innovative conceptual design of passive residual heat removal system.DOI
405. Mei-yin Zheng, W. Tian, Xiao Chu, Dalin Zhang, Ying-Wei Wu, S. Qiu, G. Su (2014). Study of traveling wave reactor (TWR) and CANDLE strategy: A review work.DOI
406. Yonghong Tian, W. Tian, Dalin Zhang, G. Su, S. Qiu (2014). Safety Analyses for Pb-Bi-Cooled Direct Contact Boiling Water Fast Reactor (PBWFR).DOI
407. Jing Zhang, Dahuan Zhu, W. Tian, S. Qiu, G. Su, Dalin Zhang (2014). Depressurization study of supercritical fluid blowdown from simple vessel.DOI
408. Cheng-Long Wang, Dalin Zhang, S. Qiu, W. Tian, G. Su (2014). CFD Analysis of Subcooled Wall Boiling at Shell Side of Steam Generator With TSP.DOI
409. Dalin Zhang, Zhipeng Zhai, A. Rineiski, Zhangpeng Guo, Cheng-Long Wang, Yao Xiao, S. Qiu (2014). COUPLE, A Time-Dependent Coupled Neutronics and Thermal-Hydraulics Code, and its Application to MSFR.DOI
410. Jian-Jun Zhou, Dalin Zhang, S. Qiu, G. Su, W. Tian, Ying-Wei Wu (2014). Three dimensional neutronic/thermal-hydraulic coupled simulation of MSR in transient state condition.DOI
411. 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》.
412. 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》.
413. Zicheng Qiu, Zai-Yong Ma, S. Qiu, Ying-Wei Wu, W. Tian, G. Su, Dalin Zhang (2013). Experimental research on the incipient boiling wall superheat of sodium.DOI
414. Dalin Zhang, Xue-Nong Chen, M. Flad, Andrei Rineiski, W. Maschek (2013). Theoretical and numerical studies of TWR based on ESFR core design.DOI
415. Zhangpeng Guo, Dalin Zhang, Yao Xiao, W. Tian, G. Su, S. Qiu (2013). Simulations of unprotected loss of heat sink and combination of events accidents for a molten salt reactor.DOI
416. Zhang-Li Wang, W. Tian, G. Su, S. Qiu, L. Zhao, Qiao-Lin Zuo, Ying-Wei Wu, Dalin Zhang (2013). Development of a thermal hydraulic code for an integral reactor.DOI
417. Zhangpeng Guo, Cheng-Long Wang, Dalin Zhang, K. Chaudri, W. Tian, G. Su, S. Qiu (2013). The effects of core zoning on optimization of design analysis of molten salt reactor.DOI
418. Zhangpeng Guo, Jian-Jun Zhou, Dalin Zhang, K. Chaudri, W. Tian, G. Su, S. Qiu (2013). Coupled Neutronics/Thermal-Hydraulics for Analysis of Molten Salt Reactor.DOI
419. Cheng-Long Wang, Dalin Zhang, S. Qiu, W. Tian, Ying-Wei Wu, G. Su (2013). Study on the characteristics of the sodium heat pipe in passive residual heat removal system of molten salt reactor.DOI
420. B. Vezzoni, F. Gabrielli, A. Rineiski, M. Marchetti, W. Maschek, Dalin Zhang, A. Schwenk-Ferrero, V. Romanello, M. Salvatores, G. Forasassi (2013). Analysis of minor actinides incineration adopting an innovative fast reactor concept.
421. Cheng-Long Wang, Zhangpeng Guo, Dalin Zhang, S. Qiu, W. Tian, Ying-Wei Wu, G. Su (2013). Transient behavior of the sodium–potassium alloy heat pipe in passive residual heat removal system of molten salt reactor.DOI
422. 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
423. Barbara Vezzoni, Fabrizio Gabrielli, Andrei Rineiski, Marco Marchetti, Xue-Nong Chen, Michael Flad, Werner Maschek, Claudia Matzerath Boccaccini, Dalin Zhang (2012). Safety-Related Optimization and Analyses of an Innovative Fast Reactor Concept. Sustainability, Vol. 40, No. 60.DOI
424. Dalin Zhang, Xue-Nong Chen, F. Gabrielli, A. Rineiski, W. Maschek (2012). Numerical Studies of Axial Fuel Shuffling.DOI
425. Xue-Nong Chen, E. Kiefhaber, Dalin Zhang, W. Maschek (2012). Fundamental solution of nuclear solitary wave.DOI
426. B. Vezzoni, Xue-Nong Chen, Michael Flad, F. Gabrielli, M. Marchetti, Werner Maschek, C. Boccaccini, Andrei Rineiski, Dalin Zhang (2012). Optimization of Safety Parameters and Accident Mitigation Measures for Innovative Fast Reactor Concepts.DOI
427. Yao Xiao, Dalin Zhang, Zhangpeng Guo, S. Qiu (2012). Numerical Analysis for a Molten Salt Reactor in the Presence of Fissile Lump.DOI
428. Xue-Nong Chen, Dalin Zhang, Werner Maschek (2012). Theoretical Modeling of Radial Standing Wave Reactor.DOI
429. Yao Xiao, Dalin Zhang, Zhangpeng Guo, Ying-Wei Wu, W. Tian, G. Su, S. Qiu (2012). Numerical analysis for a molten salt reactor in the presence of localized perturbations.DOI
430. W. Maschek, M. Flad, C. Boccaccini, S. Wang, F. Gabrielli, V. Kriventsev, Xue-Nong Chen, Dalin Zhang, K. Morita (2011). Prevention and mitigation of severe accident developments and recriticalities in advanced fast reactor systems.DOI
431. Xue-Nong Chen, Dalin Zhang, W. Maschek (2011). FUNDAMENTAL BURN-UP MODES OF RADIAL FUEL SHUFFLING.
432. Dalin Zhang, Xue-Nong Chen, F. Gabrielli, A. Rineiski, W. Maschek, T. Schulenberg (2011). Numerical studies of nuclear traveling waves in a supercritical water cooled fast reactor.DOI
433. Xue-Nong Chen, Dalin Zhang, W. Maschek, T. Schulenberg (2010). Solitary breeding/burning waves in a supercritical water cooled fast reactor.DOI
434. Peng Wang, Li-Bo Qian, Dalin Zhang, W. Tian, G. Su, S. Qiu (2010). Study on the Coupled Neutronic and Thermal-Hydraulic Characteristics of the New Concept Molten Salt Reactor.DOI
435. Li-Bo Qian, S. Qiu, Dalin Zhang, G. Su, W. Tian (2010). Numerical research on natural convection in molten salt reactor with non-uniformly distributed volumetric heat generation.DOI
436. 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》.
437. Dalin Zhang, A. Rineiski, S. Qiu (2009). Comparison of Modeling Options for Delayed Neutron Precursor Movement in a Molten Salt Reactor.
438. Dalin Zhang, S. Qiu, G. Su (2009). Development of a safety analysis code for molten salt reactors.DOI
439. Dalin Zhang, S. Qiu, G. Su, C.-L. Liu (2009). Development of a steady state analysis code for a molten salt reactor.DOI
440. Dalin Zhang, S. Qiu, G. Su, C.-L. Liu, Li-Bo Qian (2009). Analysis on the neutron kinetics for a molten salt reactor.DOI
441. Li-Bo Qian, S. Qiu, Dalin Zhang, G. Su (2009). Natural Convection With Non-Uniform Heat Generation in Molten Salt Reactor.DOI
442. 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》.
443. 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》.
444. Dalin Zhang, S. Qiu, Chang-Liang Liu, Guang-Hui Su (2008). Steady state investigation on neutronics of a molten salt reactor considering the flow effect of fuel salt.DOI
445. Dalin Zhang, Chang-Liang Liu, Li-Bo Qian, G. Su, S. Qiu (2008). Numerical Research on Steady Coupling of Neutronics and Thermal-Hydraulics for a Molten Salt Reactor.DOI
446. Dalin Zhang, S. Qiu, G. Su, D. Jia (2008). Evaluation of Static Thermophysical Properties of the Ternary Molten Salt System Li, Na and Be/F Based on the Modified Peng-Robinson Equation.DOI
447. Dalin Zhang, S. Qiu (2008). Steady Thermal Hydraulics Analysis for a Graphite-Moderated Channel Type Molten Salt Reactor.DOI
448. Dalin Zhang, S. Qiu, C.-L. Liu, G. Su (2008). Steady thermal hydraulic analysis for a molten salt reactor.DOI
449. Dalin Zhang, S. Qiu, G. Su, D. Jia (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.DOI
450. Dalin Zhang, S. Qiu, G. Su, D. Jia (2007). Estimation of thermodynamic properties of the ternary molten salt system, LiF-NaF-BeF2, by the modified Peng-Robinson equation.DOI
451. 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》.
452. Shuowang Fan, Yu-Tong Chen, Dalin Zhang, Jian Deng, Xi-Si Zhang, Xiaoli Wu, W. Tian, S. Qiu, G. Su. Experimental study on fragmentation characteristics of molten stainless steel discharged into liquid Lead-Bismuth Eutectic pool. Annals of Nuclear Energy.DOI
453. Yan Zhang, Bo Wang, Dalin Zhang, Cheng-Long Wang, Yang Yang, Zheng-Rong Guo, W.-X. Tian, G. Su, Sui-Zheng Qiu. Coupled analysis of oxidation corrosion and heat transfer in lead-cooled fast reactors. Annals of Nuclear Energy.DOI
454. Dingsheng Lu, Yupeng Yang, Xiao Pang, Cheng-Long Wang, Dalin Zhang, Suizheng Qiu. Effect of impurity deposition on the thermal-hydraulic performance of an LBE/water single-pass counter-current steam generator. International journal of thermal sciences.DOI

预印本

1. 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
2. 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
3. Hao Sun, Yong Ouyang, Jiawei Bian, Chenglong Wang, Dalin Zhang, Zhikang Lin (2024). Development of a Numerical Thermal Analysis Model for Wick-Type Heat Pipe Under Swing Conditions. SSRN Electronic Journal.DOI
4. 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

书籍章节

1. Dalin Zhang (2023). Generation-IV concepts: China. Elsevier eBooks.DOI
2. 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
3. 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
4. Dalin Zhang (2016). Generation IV concepts. Elsevier eBooks.DOI