百晓学者学者目录

曹学武

上海交通大学机械与动力工程学院

精选作品

期刊论文

  1. Junji Chen, Lili Tong, Xuewu Cao (2026). Interpretable prediction of condensation heat transfer coefficient using a residual fully connected neural network. Annals of Nuclear Energy.DOI
  2. Shu Li, Dan-Di Zhang, Li-Li Tong, Xue-Wu Cao (2026). Experimental study on hydrodynamic loads during air clearing process of safety relief system for NHR200-II reactor. Annals of Nuclear Energy.DOI
  3. Qiang Lv, Peizheng Hu, Li-Li Tong, Xue-Wu Cao (2026). Aerosol Removal by Spray Nozzles: Mechanical Efficiency and Modeling. Journal of Aerosol Science.DOI
  4. Jing-Hua Jiang, Xue-Wu Cao, Shuan Xia, Jian-Hui Yu, Yuan-Lei He, Jing-Huai Li, Zheng-Feng Sha, Jin-Kun Zhao (2026). Three-dimensional CFD analysis of in-vessel LOCA induced by a highly under-expanded helium jet in the vacuum vessel. Alexandria Engineering Journal.DOI
  5. 刘昭然，李澍，佟立丽，曹学武（2025）. 核反应堆一回路超压泄放载荷影响因素研究. 《强激光与粒子束》.
  6. 吕强，田超，佟立丽，曹学武（2025）. 浸没射流高韦伯数条件下气溶胶水洗去除. 《强激光与粒子束》.
  7. Xuesong Bai, Lili Tong, Xuewu Cao (2025). Eutectic melting characteristics in B₄C–316L stainless steel system under rapid heating. Journal of Nuclear Materials.DOI
  8. Jinghua Jiang, Lili Tong, Xuewu Cao (2025). Improvement of impinging jet heat transfer model for thermal-hydraulic analysis in the vacuum vessel of a fusion reactor. Fusion Engineering and Design.DOI
  9. Jinghua Jiang, Jun He, Tianyu Chen, Lili Tong, Xuewu Cao, Songlin Liu (2025). Numerical study of thermohydraulics induced by highly under-expanded jet during in-vessel LOCA for the CFETR WCCB concept. Nuclear Fusion.DOI
  10. Peizheng Hu, Zhichao Gao, Yi-Xin Huang, Li-Li Tong, Xue-Wu Cao (2025). Semi-empirical model for resuspension of multilayer sedimentary aerosols in pipes. Annals of Nuclear Energy.DOI
  11. 惠天宇，佟立丽，曹学武（2024）. 基于多孔介质方法的钠冷快堆冷却剂沸腾现象模拟. 《强激光与粒子束》.
  12. 邹文斌，佟立丽，曹学武（2024）. 均匀碎片床与分层碎片床干涸现象及热流密度实验研究. 《核动力工程》.
  13. Wenbin Zou, Yuzeng Wu, Tianyu Chen, Huancheng Jin, Lili Tong, Xuewu Cao (2024). An improved model of pressure drops in gas–water two-phase flow through packed debris beds for wide void fraction. Annals of Nuclear Energy.DOI
  14. Peizheng Hu, Lili Tong, Xuewu Cao (2024). Investigation on aerosol removal by spray droplets under severe accident conditions. Progress in Nuclear Energy.DOI
  15. Dandi Zhang, Wang Shanpu, Tong Lili, Cao Xuewu (2024). Retention analysis of aerosol inside narrow channels of the containment. Annals of Nuclear Energy.DOI
  16. Kwang-Il Ahn, Federico Mezio, Shawkat Ali, Xuewu Cao, Young Jin Cho, Bassam A. Khuwaileh, Víctor Martínez-Quiroga, F. Mascari, F. Gabrielli, David Luxat, Tatjana Jevremović (2024). Uncertainty and Sensitivity Analyses for Postulated Severe Accidents of Reference PWRs and SMRs in the Frame of the IAEA CRP and Relevant Insights. Nuclear Technology.DOI
  17. Wenbin Zou, Zhaoran Liu, Lili Tong, Xuewu Cao (2024). Investigations on the Debris Bed Formation Behavior of the Heated Solid Particles.DOI
  18. Jinghua Jiang, Peizheng Hu, Lili Tong, Xuewu Cao (2024). Numerical Study of Gas Flow and Diffusion Driven by Buoyancy in a Multi-Openings Compartment.DOI
  19. Dandi Zhang, Shu Li, Lili Tong, Xuewu Cao (2024). Research on heat transfer characteristics of steam condensation with non-condensable gas at low steam mass flux. Applied Thermal Engineering.DOI
  20. Hong Q. Ding, Peizheng Hu, Wenbin Zou, Zhizhou Zhu, Tong Lili, Xuewu Cao (2024). Experimental study of aerosol diffusiophoresis deposition in steel containment under external cooling measures. International Journal of Advanced Nuclear Reactor Design and Technology.DOI
  21. 李玉祥，吴艳，曹学武（2023）. 不同流型下气溶胶水洗效果影响因素实验研究. 《原子能科学技术》.
  22. 徐震，胡培政，佟立丽，曹学武（2023）. 基于不稳定波理论的钠雾化粒径预测研究. 《核动力工程》.
  23. 姜京华，曹学武（2023）. 聚变堆失真空事故下氚的大气扩散模拟研究. 《核技术》.
  24. 方闻韬，佟立丽，曹学武（2023）. 绕丝交混模型对钠冷快堆组件子通道分析的影响. 《强激光与粒子束》.
  25. 邱志方，郭容达，曹学武，余红星，孙洪平，罗跃建（2023）. 小型压水堆抑压特性试验与数值模拟研究. 《核动力工程》.
  26. 方闻韬，佟立丽，曹学武（2023）. 钠冷快堆组件冷却剂沸腾子通道分析方法研究. 《核科学与工程》.
  27. 胡培政，王善普，佟立丽，曹学武（2023）. 微小通道内流动及气溶胶沉积特性实验研究. 《原子能科学技术》.
  28. Zhen Xu, Lili Tong, Xuewu Cao (2023). Prediction of sodium leakage droplet size distribution in sodium-cooled fast reactor loop. Progress in Nuclear Energy.DOI
  29. Zhitong Yu, Dandi Zhang, Lili Tong, Xuewu Cao (2023). Analysis method for aerosol deposition behavior under sodium spray fire. Progress in Nuclear Energy.DOI
  30. Liwen He, Lili Tong, Xuewu Cao (2023). Study on aerosol thermophoretic force and thermophoresis deposition model in reactor building. Progress in Nuclear Energy.DOI
  31. Peizheng Hu, Shanpu Wang, Lili Tong, Xuewu Cao (2023). Aerosol turbulent deposition characteristics under small and micro-scaled leakage paths. Annals of Nuclear Energy.DOI
  32. Shanpu Wang, Lili Tong, Xuewu Cao (2023). Effect of tortuosity on retention of aerosol particles through small curved concrete cracks. Progress in Nuclear Energy.DOI
  33. Zhenyu Zou, Lili Tong, Xuewu Cao (2023). Droplet group combustion model improvement for sodium spray fire pre-combustion analysis. Annals of Nuclear Energy.DOI
  34. Tianlin Wang, Lili Tong, Xuewu Cao (2023). A universal correlation development for film-wise condensation in the presence of non-condensable gases on vertical walls under turbulent free convection. Annals of Nuclear Energy.DOI
  35. Zhifang Qiu, Hongxing Yu, Qingwen Xiong, Xuewu Cao, Lili Tong (2023). Uncertainty and sensitivity analysis of the DVI line break loss of coolant accident for small modular reactor. Progress in Nuclear Energy.DOI
  36. Jinghua Jiang, Yuanchen Qin, Lili Tong, Xuewu Cao, Songlin Liu, Xiaoman Cheng (2023). Phenomena Identification and Ranking Table for Thermal-Hydraulic Safety of China Fusion Engineering Test Reactor. Fusion Science & Technology.DOI
  37. Zhichao Gao, Yongzheng Chen, Dandi Zhang, Peng Chen, Lili Tong, Xuewu Cao (2023). Study of poly-disperse aerosols deposition in turbulent flow with different Reynolds numbers. Particuology.DOI
  38. Wenbin Zou, Lili Tong, Xuewu Cao (2023). Study on dryout heat flux of axial stratified debris bed under top-flooding. Nuclear Engineering and Technology.DOI
  39. Dandi Zhang, Shanpu Wang, Lili Tong, Xuewu Cao (2023). Experimental investigation on thermal stratification characteristic of steam condensation through multi-hole sparger. Applied Thermal Engineering.DOI
  40. Liwen He, Lili Tong, Xuewu Cao (2023). Study on Resuspension Models Based on Force Balance. Springer proceedings in physics.DOI
  41. Wenbin Zou, Xue‐Song Bai, Lili Tong, Xuewu Cao (2023). EXPERIMENTAL INVESTIGATION ON DRYOUT PHENOMENON OF HOMOGENEOUS AND AXIAL STRATIFIED DEBRIS BED. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
  42. Zhen Xu, Peizheng Hu, Lili Tong, Xuewu Cao (2023). EXPERIMENTAL STUDY ON SPRAY CHARACTERISTICS OF HOLLOW CONE NOZZLE. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
  43. Tianyu Hui, Wentao Fang, Lili Tong, Xuewu Cao (2023). SIMULATION OF SODIUM BOILING PHENOMENON BASED ON POROUS MEDIUM APPROACH AND TWO-FLUID MODEL. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
  44. Zhitong Yu, Yuanchen Qin, Lili Tong, Xuewu Cao (2023). Validation of Lumped Parameter Code for Aerosol Behavior Analysis in Containment. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
  45. Yuanchen Qin, Jinghua Jiang, Xuewu Cao, Pengfeï Liu (2023). NUMERICAL STUDY OF HELIUM HIGHLY UNDER-EXPANDED JET INDUCED BY INVESSEL LOCA FOR FUSION REACTOR. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
  46. 郭容达，张丹迪，曹学武（2022）. 抑压水池温度分层影响因素. 《强激光与粒子束》.
  47. 俞之桐，曹学武（2022）. 钠工艺间钠雾火模型适用性分析. 《核技术》.
  48. 邹文斌，佟立丽，曹学武（2022）. 基于最大熵原理的钠液滴粒径分布模型开发. 《核科学与工程》.
  49. 王善普，佟立丽，曹学武（2022）. 钢制安全壳窄缝内气溶胶冷凝滞留实验研究. 《核动力工程》.
  50. 郭丁情，王韶轩，林志贤，戈道川，曹学武（2022）. 动态故障树在主蒸汽管道破裂事故风险评价中的初步应用研究. 《原子核物理评论》.
  51. Zhan Gao, D.D. Zhang, Lili Tong, Xuewu Cao (2022). Aerosol pool scrubbing phenomena during the containment depressurization venting. Part Ⅱ: Test facility and test result. Annals of Nuclear Energy.DOI
  52. Dandi Zhang, Zhifang Qiu, Lili Tong, Xuewu Cao (2022). Experimental investigation on the steam condensation dynamic characteristics at low steam mass flux. Annals of Nuclear Energy.DOI
  53. Liwen He, Lili Tong, Xuewu Cao (2022). Investigation of aerosol resuspension model based on random contact with rough surface. Nuclear Engineering and Technology.DOI
  54. Dandi Zhang, Lili Tong, Xuewu Cao (2022). Condensation oscillation characteristic of steam with non-condensable gas through multi-hole sparger at low mass flux. Nuclear Engineering and Technology.DOI
  55. Ying Li, Jinghua Jiang, Lili Tong, Xuewu Cao (2022). Analytical investigation of hydrogen distribution with steam condensation in confined vessel. International Journal of Energy Research.DOI
  56. Shanpu Wang, Yuxiang Li, Liwen He, Lili Tong, Xuewu Cao (2022). Experimental Study on Aerosol Penetration Through Concrete Cracks Under Inertial Collision and Steam Condensation. Volume 15: Student Paper Competition.DOI
  57. Jinghua Jiang, Ying Li, Tianlin Wang, Lili Tong, Xuewu Cao (2022). Mixing and Stratification Phenomena Under Natural Convection in the Multi-Openings Compartment.DOI
  58. Dingqing Guo, Shaoxuan Wang, Daochuan Ge, Lili Tong, Xuewu Cao (2022). Reliability Analysis of Active Reactor Pit Flooding Function of EHR DFT System of a NPP Using an Enhanced Component-Connection Method.DOI
  59. Ming Wang, Dingqing Guo, Fei Wang, Zhixin Xu, Bing Zhang, Jinkai Wang, Lili Tong, Xuewu Cao (2022). Radioactive Substance Release Risk Assessment for Fuel Mechanical Damage in Fuel Route.DOI
  60. Yuxiang Li, Yan Yang Wu, Xuewu Cao (2022). Influence of Jet on Aerosol Retention by Pool Scrubbing Under Multihole Injector. Frontiers in Energy Research.DOI
  61. Tianlin Wang, Lili Tong, Xuewu Cao (2022). Improvement of diffusion layer model for steam condensation in the presence of non-condensable gas under turbulent free convection. Applied Thermal Engineering.DOI
  62. 王学栋，郭丁情，佟立丽，曹学武（2021）. 核电厂严重事故下辐射环境蒙特卡罗模拟及方法应用研究. 《核科学与工程》.
  63. 王俊豪，李玉祥，高圣钦，佟立丽，曹学武（2021）. 气溶胶水洗过滤效率实验研究. 《核科学与工程》.
  64. 涂卓，曹学武（2021）. 湍流情况下气溶胶微小通道沉积规律数值模拟研究. 《核科学与工程》.
  65. 袁璐，曹学武（2021）. 核电厂严重事故下氢气源项的不确定性分析. 《原子能科学技术》.
  66. 汪孝凡，曹学武（2021）. 安全壳外挂水箱结构强度分析. 《原子能科学技术》.
  67. 李航，曹学武（2021）. 振荡区下蒸汽冷凝过程的热工水力模型建立及验证. 《原子能科学技术》.
  68. 王田林，曹学武（2021）. 空间中氦气与氢气分布相似性分析. 《核科学与工程》.
  69. Zhan Gao, Zhifang Qiu, Lili Tong, Xuewu Cao (2021). Aerosol pool scrubbing phenomena during the containment depressurization venting. Part I: Scaling analysis. Annals of Nuclear Energy.DOI
  70. Dandi Zhang, Lili Tong, Xuewu Cao (2021). Experimental study on flow oscillating mechanism of non-condensable gas jet through one- or multi-hole sparger in quiescent water. Annals of Nuclear Energy.DOI
  71. Yue Li, Lili Tong, Xuewu Cao (2021). Experimental study on gas mixing and transport induced by external cooling on large-scale facility. Annals of Nuclear Energy.DOI
  72. Dingqing Guo, Manjiang Yang, Hongmei Wu, Daochuan Ge, Xuewu Cao (2021). Dynamic Reliability Evaluation of Diesel Generator System of One Chinese 1000MWe NPP Considering Temporal Failure Effects. Frontiers in Energy Research.DOI
  73. Liming He, Yuxiang Li, Yihui Zhou, S. Chen, L. L. Tong, Xuewu Cao (2021). Investigation on Aerosol Pool Scrubbing Model During Severe Accidents. Frontiers in Energy Research.DOI
  74. Yuxiang Li, Lili Tong, Xuewu Cao (2021). Experimental Study on Influencing Factors of Aerosol Retention by Pool Scrubbing. Frontiers in Energy Research.DOI
  75. Tianlin Wang, Di Wang, Lili Tong, Xuewu Cao (2021). Improvement of Condensation Model With the Presence of Non-Condensable Gas for Thermal-Hydraulic Analysis in Containment. Frontiers in Energy Research.DOI
  76. 李颖，侯丽强，杨帆，曹学武（2020）. 氢气迁移扩散二维模型分析. 《核科学与工程》.
  77. 何丽雯，侯丽强，佟立丽，曹学武（2020）. 基于REVENT实验的气溶胶再夹带模型适用性分析. 《核技术》.
  78. 戚雄飞，侯丽强，杜政瑀，曹学武（2020）. 单隔间内氢气流动分布特性数值模拟与实验验证. 《强激光与粒子束》.
  79. 高志超，曹学武（2020）. 安全壳卸压排放过程模化分析. 《原子能科学技术》.
  80. 周彦，佟立丽，曹学武（2020）. 低流速排放下气溶胶水洗模型. 《原子能科学技术》.
  81. Lili Tong, Dingqing Guo, Di Wang, Xuewu Cao (2020). Improvements of turbulence model for analysis of hydrogen stratification erosion by turbulent buoyant jet. Annals of Nuclear Energy.DOI
  82. Lili Tong, T.L. Wang, Jian Deng, Xuewu Cao (2020). Multi-module program for small-leak sodium–water reaction analysis in steam generators of sodium-cooled fast reactors. Progress in Nuclear Energy.DOI
  83. Lili Tong, L.Q. Hou, Xuewu Cao (2020). Analysis of the flow distribution and mixing characteristics in the reactor pressure vessel. Nuclear Engineering and Technology.DOI
  84. Tianlin Wang, Lili Tong, Xuewu Cao (2020). Numerical Investigation of the Obstacle on Hydrogen Distribution in a Vessel.DOI
  85. Ying Li, Wei Xue, Xuewu Cao, Lili Tong (2020). Experimental Investigation on Gas Mixing and Stratification in Containment Influenced by External Cooling.DOI
  86. Hanchen Liu, Lili Tong, Xuewu Cao (2020). Experimental study on hydrogen behavior and possible risk with different injection conditions in local compartment. Nuclear Engineering and Technology.DOI
  87. Lili Tong, Jian Deng, Xuewu Cao (2020). Numerical investigation on erosion of hydrogen stratification by steam jet within a local compartment. International Journal of Energy Research.DOI
  88. Li-Li Tong, C. Peng, Xue-Wu Cao (2020). One-dimensional model of hydrogen distribution in confined space based on Froude number.DOI
  89. 王学栋，曹学武，赵晓玲（2019）. 重水堆核电厂严重事故下辐射环境模拟. 《核动力工程》.
  90. 邓欣洁，曹学武（2019）. 钠冷快堆蒸汽发生器小泄漏事故中氢迁移行为研究. 《核技术》.
  91. 何丽雯，佟立丽，曹学武（2019）. 基于STORM实验的气溶胶再悬浮模型适用性分析. 《核技术》.
  92. 杜政瑀，佟立丽，曹学武，王小吉，侯丽强（2019）. 重力注水流动不稳定现象关键影响因素实验研究（英文）. 《核动力工程》.DOI
  93. 杜政瑀，佟立丽，曹学武，王小吉，侯丽强（2019）. 重力注水过程流动不稳定现象关键影响因素研究. 《原子能科学技术》.
  94. 游曦鸣，佟立丽，曹学武（2019）. 液态金属与冷却剂相互作用机械能释放模型分析. 《核科学与工程》.
  95. Di Wang, Lili Tong, Luguo Liu, Xuewu Cao, Zhiqiang Zou, Lingjun Wu, Xiaowei Jiang (2019). Preliminary numerical study on hydrogen distribution characteristics in the process that flow regime transits from jet to buoyancy plume in time and space. Nuclear Engineering and Technology.DOI
  96. 王迪，佟立丽，曹学武，邹志强，陈树（2018）. 对流换热模型对局部氢气流动影响的数值研究. 《核动力工程》.
  97. Dong Wang, Lili Tong, Xuewu Cao (2018). Numerical study on the influence of steam condensation on hydrogen distribution in local compartments. Annals of Nuclear Energy.DOI
  98. Zhong Fang, Xuewu Cao, Lili Tong, Yusa Muroya, G. Whitaker, Mojtaba Momeni, Mingzhang Lin (2018). An improved method for modelling coolant radiolysis in ITER. Fusion Engineering and Design.DOI
  99. Zhong Fang, Jia Tang, Jiaxin Xiao, Lili Tong, Xuewu Cao, Hanqin Weng, Mingzhang Lin (2018). Modelling electrical corrosion potential of 304 stainless steel under fusion power plant environment. Journal of Radioanalytical and Nuclear Chemistry.DOI
  100. Cheng Peng, Lili Tong, Xuewu Cao (2018). Numerical Analysis on Characteristic of Hydrogen Mixing and Stratification in a Containment Model.DOI
  101. Xinjie Deng, Xuewu Cao (2018). Study on Hydrogen Migration in Small Water Leak of Sodium-Cooled Fast Reactor.DOI
  102. Li-Li Tong, X. Zhou, Xue-Wu Cao (2018). Ultimate pressure bearing capacity analysis for the prestressed concrete containment. Annals of Nuclear Energy.DOI
  103. 彭程，佟立丽，曹学武（2017）. 高熔点物质与冷却剂相互作用的机理研究. 《核科学与工程》.
  104. 杨生兴，佟立丽，曹学武，王小吉，侯丽强（2017）. 基于RELAP5的高温棒束通道再淹没数值模拟研究. 《核科学与工程》.
  105. 胡效明，佟立丽，曹学武（2017）. 安全壳模型装置内氢气分布特性及影响因素分析. 《核科学与工程》.
  106. 刘辰，曹学武（2017）. 水冷氚增殖包层的中子学模拟. 《核聚变与等离子体物理》.
  107. 游曦鸣，佟立丽，曹学武（2017）. 熔融锂液滴与冷却剂在不同温度下的相互作用实验研究. 《核科学与工程》.
  108. 周璇，佟立丽，曹学武（2017）. 水冷包层模块第一壁流动传热特性初步分析. 《核科学与工程》.
  109. Dong Wang, Xuewu Cao (2017). Numerical analysis of different break direction effect on hydrogen behavior in containment during a hypothetical LOCA. Annals of Nuclear Energy.DOI
  110. Di Wang, Xuewu Cao (2017). Preliminary Analysis of Hydrogen Distribution During Severe Accident Induced by Loss of Coolant Accident.DOI
  111. Yabing Li, Xuewu Cao (2017). Study on Hydrogen Risk of Spent Fuel Compartment Induced by Containment Venting.DOI
  112. Hanchen Liu, Kai Yuan, Xuewu Cao (2017). Numerical Study on Hydrogen Flow Behavior for Different Connecting Pipe Structures.DOI
  113. Thambiayah Nitheanandan, Xuewu Cao, Jongho Choi, Daniel Dupleac, D.-H. Kim, H.G. Lele, Arun Kumar Nayak, H. P. Rammohan (2017). Benchmarking Severe Accident Computer Codes for Heavy Water Reactor Applications. Journal of Nuclear Engineering and Radiation Science.DOI
  114. Hanchen Liu, Xuewu Cao (2017). Numerical Study on Hydrogen Flow Behavior in Two Compartments with Different Connecting Pipes. Science and Technology of Nuclear Installations.DOI
  115. 彭程，佟立丽，曹学武，闫晓（2016）. 熔融物热细粒化的实验研究. 《核动力工程》.
  116. 廖世梁，曹学武（2016）. 水冷包层试验段设计与流动特性研究. 《核聚变与等离子体物理》.
  117. 马飞，佟立丽，曹学武，罗广南（2016）. 水蒸气对氢气燃烧影响的数值研究. 《原子能科学技术》.
  118. 王迪，曹学武（2016）. 不同湍流模型对氢气分布影响的数值研究. 《原子能科学技术》.
  119. 李亚冰，郭丁情，曹学武（2016）. 严重事故下正常余热排出系统向堆芯注水策略分析. 《原子能科学技术》.
  120. 陈金波，廖世梁，佟立丽，曹学武，邓坚，曾未（2016）. 竖直管道内间歇式两相流动沸腾特性分析. 《原子能科学技术》.
  121. 游曦鸣，邵舸，佟立丽，曹学武（2016）. 非能动堆芯冷却系统LOCA下冷却能力分析. 《原子能科学技术》.
  122. 余健明，曹学武（2016）. 先进非能动核电厂DEDVI事故热工水力模拟分析. 《核科学与工程》.
  123. 李亚冰，佟立丽，曹学武（2016）. 先进非能动压水堆防火喷淋对严重事故的缓解作用研究. 《核科学与工程》.
  124. 王迪，佟立丽，曹学武（2016）. 水冷固态增殖包层模块冷却剂管系流量分配研究. 《核科学与工程》.
  125. Cheng Peng, Lili Tong, Xuewu Cao (2016). Preliminary study on the fuel-coolant interaction triggered by thermal effect. Annals of Nuclear Energy.DOI
  126. Cheng Peng, Lili Tong, Xuewu Cao (2016). Numerical analysis on hydrogen stratification and post-inerting of hydrogen risk. Annals of Nuclear Energy.DOI
  127. Ya-Bing Li, Li-Li Tong, Xue-Wu Cao（2016）. 先進的非能動加圧式防火消火による深刻な事故への緩和作用に関する研究【JST・京大機械翻訳】.
  128. Ya-Bing Li, Li-Li Tong, Xue-Wu Cao (2016). Mitigation on Severe Accidents with Fire Spray System in Advanced Passive PWR.
  129. Fei Ma, Li-Li Tong, Xue-Wu Cao, Guang-Nan Luo（2016）. 水素の燃焼に及ぼす水蒸気の影響に関する数値的研究【JST・京大機械翻訳】.
  130. Di Wang, Li-Li Tong, Xue-Wu Cao (2016). Study on Flow Distribution of Coolant Pipes for WCSB Module.
  131. 朱伟，李亚冰，佟立丽，曹学武（2015）. 基于氢气风险分析的ADS手动卸压策略研究. 《原子能科学技术》.
  132. 邵舸，佟立丽，曹学武（2015）. 基于SCDAP/RELAP5耦合堆腔注水的非能动压水堆熔融池冷却分析. 《原子能科学技术》.
  133. 宫海光，郭丁情，佟立丽，曹学武（2015）. 重水堆核电厂典型严重事故氢气风险分析. 《核科学与工程》.
  134. 王慕飞，佟立丽，曹学武（2015）. 水冷包层模块局部模型流量分配数值模拟. 《核聚变与等离子体物理》.
  135. 朱力，陈金波，宫海光，佟立丽，曹学武（2015）. 低压加热通道内间歇式流动特性分析. 《核动力工程》.
  136. 彭程，佟立丽，曹学武，闫晓（2015）. 基于边界层剥离机理的水力学细粒化模型研究. 《核动力工程》.
  137. 侯丽强，佟立丽，曹学武，彭欢欢（2015）. 实验装置氢气混合的数值研究. 《核动力工程》.
  138. 刘文勇，刘雷雷，佟立丽，曹学武（2015）. 红外无损检测在面向等离子体部件检测的应用. 《核聚变与等离子体物理》.
  139. 陈金波，杨生兴，佟立丽，曹学武，邓坚，曾未（2015）. 系统压力对间歇式流动沸腾特性影响的实验研究. 《核科学与工程》.
  140. 刘辰，曹学武（2015）. 聚变核数据库在水冷包层模块中子学特性模拟的影响研究. 《中国核科学技术进展报告（第四卷）——中国核学会2015年学术年会论文集第7册（计算物理分卷、核物理分卷、粒子加速器分卷、核聚变与等离子体物理分卷、脉冲功率技术及其应用分卷、辐射物理分卷）》.
  141. 邵舸，佟立丽，曹学武（2015）. 压水堆核电厂严重事故卸压阀能力评估. 《核科学与工程》.
  142. 廖世梁，曹学武（2015）. 水冷包层子模块第一壁模化与数值模拟. 《中国核科学技术进展报告（第四卷）——中国核学会2015年学术年会论文集第3册（核能动力分卷（下））》.
  143. 马凤金，曹学武（2015）. 浅谈对乏燃料核电场内运输的监督. 《企业技术开发》.
  144. Yuanlong Li, Xuewu Cao (2015). Strategy evaluation for fire spray system on Advanced Passive PWR Severe Accident Management Guideline. Progress in Nuclear Energy.DOI
  145. Cheng Peng, Lili Tong, Xuewu Cao (2015). A hydrodynamic fragmentation model based on boundary layer stripping. Annals of Nuclear Energy.DOI
  146. Lili Tong, Jie Zou, Xuewu Cao (2015). Analysis on hydrogen risk mitigation in severe accidents for Pressurized Heavy Water Reactor. Progress in Nuclear Energy.DOI
  147. Lili Tong, Jie Zou, Tao Jun, Xuewu Cao (2015). Study on Heat Removal Capacity of PCCS of Advanced Passive PWR during Severe Accidents. Nuclear Technology.DOI
  148. Jinbo Chen, Shengxing Yang, Shiliang Liao, Xuewu Cao (2015). Experimental investigation of effective parameters on geyser periodicity in a vertical heated system. Experimental Thermal and Fluid Science.DOI
  149. Ge Shao, Xuewu Cao (2015). Safety analysis of increase in heat removal from reactor coolant system with inadvertent operation of passive residual heat removal at no-load conditions. Nuclear Engineering and Technology.DOI
  150. Ximing You, Xuewu Cao (2015). Study of Liquid Lithium Coolant Interaction Based on BP Neural Network Optimized by Genetic Algorithm. Journal of Fusion Energy.DOI
  151. Liqiang Hou, Lili Tong, Xuewu Cao (2015). Dust Migration Simulation During Loss of Vacuum Accident. Journal of Fusion Energy.DOI
  152. Ximing You, Lili Tong, Xuewu Cao (2015). ICONE23-1354 PREDICTION MODEL OF EXPLOSION STRENGTH OF LIQUID LITHIUM WATER INTERACTION BASED ON A BP NEURAL NETWORK. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
  153. Cheng Peng, Jianqing Liu, Xiao Yan, Xuewu Cao (2015). ICONE23-1490 STUDY ON THE THERMAL FRAGMENTATION MODEL UNDER UNSTABLE FILM BOILING CONDITION. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
  154. Xi-Ming You, Li-Li Tong, Xue-Wu Cao (2015). Preliminary experimental study of liquid lithium water interaction.DOI
  155. Yan-Kai Li, Li-Li Tong, Xue-Wu Cao, Ding-Qing Guo (2015). In-vessel retention coolability evaluation for Chinese improved 1000 MWe PWR.DOI
  156. Li-Li Tong, Guangyuan Huang, Xue-Wu Cao (2015). Simulation of fission products behavior in severe accidents for advanced passive PWR.DOI
  157. 袁凯，邹杰，佟立丽，曹学武（2014）. 非能动先进压水堆核电厂严重事故下裂变产物行为研究. 《核科学与工程》.
  158. 段蓉，佟立丽，曹学武（2014）. 先进压水堆一回路地震反应谱分析及参数敏感性研究. 《原子能科学技术》.
  159. 袁凯，曹学武，顾健，李建立，祝圆，杨杉（2014）. 压水堆核电厂安全壳过滤排放系统卸压策略分析. 《核科学与工程》.
  160. 苑景田，佟立丽，曹学武（2014）. 重水堆停堆工况下单相自然循环流动与传热分析. 《原子能科学技术》.
  161. 苑景田，佟立丽，曹学武（2014）. 重水堆停堆工况下单相自然循环热阱有效性分析. 《核科学与工程》.
  162. 佟立丽，曹学武（2014）. 气溶胶模型对安全壳旁路释放类事故源项的影响. 《核科学与工程》.
  163. 邹杰，佟立丽，曹学武（2014）. 典型严重事故非能动安全壳冷却系统效果分析. 《北京核学会第十届（2014年）核应用技术学术交流会》.
  164. 侯丽强，佟立丽，曹学武（2014）. 聚变装置失真空事故下灰尘迁移的数值研究. 《北京核学会第十届（2014年）核应用技术学术交流会论文集》.
  165. Lili Tong, Jinbo Chen, Xuewu Cao, Shengxing Yang, Shiliang Liao, Jian Deng, Wei Zeng (2014). Visualization experiments on the geyser boiling-induced instability in vertical circular tube at low-pressures. Annals of Nuclear Energy.DOI
  166. Lili Tong, Rong Duan, Xuewu Cao (2014). Seismic analysis of RCS with finite element model for advanced PWR. Progress in Nuclear Energy.DOI
  167. Gaofeng Huang, Lili Tong, Xuewu Cao (2014). Study on mitigation of ex-vessel release of fission products in severe accidents for Chinese two loops PWR. Progress in Nuclear Energy.DOI
  168. Gaofeng Huang, Lili Tong, Xuewu Cao (2014). A simplified approach to evaluating severe accident source term for PWR. Annals of Nuclear Energy.DOI
  169. Lili Tong, G. Shao, M.F. Wang, Xuewu Cao (2014). Safety evaluation of the modified auxiliary feedwater system for the Chinese improved PWR. Annals of Nuclear Energy.DOI
  170. K. Yuan, Dingqing Guo, Lili Tong, Xuewu Cao (2014). Evaluation of containment venting strategy via VFS path for advanced passive PWR NPP. Progress in Nuclear Energy.DOI
  171. Lili Tong, Yabing Li, Jianming Yu, Xuewu Cao (2014). Preliminary Analysis of In-Vessel First Wall Cooling Pipe Ruptures for ITER. Journal of Fusion Energy.DOI
  172. Lili Tong, Liqiang Hou, Xuewu Cao (2014). Study on Hydrogen Risk Induced by Dust for Fusion Device. Journal of Fusion Energy.DOI
  173. Lili Tong, Mufei Wang, Xuewu Cao (2014). Flow Distribution Analysis of Water-Cooled Solid Breeder Test Blanket Module. Journal of Fusion Energy.DOI
  174. Ximing You, Lili Tong, Xuewu Cao (2014). The Design of Experiment Equipment for Liquid Lithium Water Interaction.DOI
  175. Yabing Li, Lili Tong, Xuewu Cao (2014). Influence of RCS Depressurization Strategy on Hydrogen Risk.DOI
  176. Jie Zou, Lili Tong, Xuewu Cao (2014). Study of Decay Heat Removal Approach for Advanced Passive PWR During Station Blackout.DOI
  177. Jinbo Chen, Lili Tong, Xuewu Cao, Jian Deng, Wei Zeng (2014). Study on intermittent flow behavior in a vertical channel under low-pressure condition. Journal of Nuclear Science and Technology.DOI
  178. Li-Li Tong, Jia-Yue Chen, Xue-Wu Cao, J. Deng (2014). Thermal hydraulic behavior under Station Blackout for CANDU6.DOI
  179. J. Zou, Q. Li, Li-Li Tong, Xue-Wu Cao (2014). Assessment of passive residual heat removal system cooling capacity.DOI
  180. 邵舸，佟立丽，曹学武（2013）. 反应堆主回路卸压对压力容器外裂变产物释放的影响分析. 《原子能科学技术》.
  181. 戚展飞，陈金波，佟立丽，曹学武（2013）. 加热系统间歇泉流动机理与模型研究. 《原子能科学技术》.
  182. 邹杰，佟立丽，曹学武，顾健，薛峻峰，江宇，郝禄禄，仇苏辰，刘力（2013）. 百万千瓦级压水堆严重事故下氢气源项及氢气控制有效性分析. 《核动力工程》.
  183. 戚展飞，陈金波，佟立丽，曹学武（2013）. 加热系统间歇泉流动特征及影响因素实验研究. 《核动力工程》.
  184. 李若晴，佟立丽，曹学武（2013）. ITER第一壁冷却剂管道断裂事故热工水力初步分析. 《核聚变与等离子体物理》.
  185. 刘雷雷，佟立丽，蒋校丰，曹学武（2013）. 聚变灰尘实验装置STARDUST失真空事故的数值模拟. 《核聚变与等离子体物理》.
  186. Lili Tong, G. Shao, K. Yuan, Xuewu Cao (2013). An experimental study on geysering phenomena induced by buoyancy in a heating system. Annals of Nuclear Energy.DOI
  187. Rong Duan, Lili Tong, Xuewu Cao (2013). Seismic Response Spectrum Analysis on Advanced PWR Coolant System. Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors.DOI
  188. Yabing Li, Lili Tong, Xuewu Cao (2013). A Design Proposal and Assessment of In-Vessel Retention Strategy for 2nd Generation PWR.DOI
  189. Hong Gao, Feng Gao, Xianchao Zhao, Jie Chen, Xuewu Cao (2013). Flow Transient in Primary Coolant System During Reactor Coolant Pump Start-Up Period.DOI
  190. Ge Shao, Lili Tong, Xuewu Cao (2013). Assessment of Severe Accident Depressurization Valve Activation Strategy for Chinese Improved 1000 MWe PWR. Science and Technology of Nuclear Installations.DOI
  191. Xue-Wu Cao, Li-Li Tong, Jin-bo Chen, Hai-Guang Gong, J. Zou (2013). Nuclear reactor outage analog system and method thereof.
  192. J. Tao, Xue-Wu Cao (2013). Effect of water injection on hydrogen generation during severe accident in PWR.DOI
  193. K. Yuan, W. Qie, Li-Li Tong, Xue-Wu Cao (2013). Analysis on containment depressurization under severe accidents for a Chinese 1000 MWe NPP.DOI
  194. Xue-Wu Cao (2013). Experimental Study on Flow Characteristics and Parameters Influences of Geysering Phenomena in Heating System.
  195. Xue-Wu Cao (2013). Geysering Mechanism and Model Study for Heating System.
  196. Jing-Xi Li, Li-Li Tong, Xue-Wu Cao (2013). Effect of hydrogen combustion in the primary pump compartment.DOI
  197. Xue-Wu Cao (2013). Preliminary analysis of the thermal-hydraulic behavior induced by first wall coolant pipe leakage accidents for ITER.
  198. Xue-Wu Cao (2013). Numerical simulation of loss of vacuum accident in STARDUST.
  199. 鲍依兰，黄高峰，佟立丽，曹学武（2012）. 贝叶斯网络用于屏蔽泵系统故障分析方法的研究. 《核科学与工程》.
  200. 戚展飞，佟立丽，曹学武（2012）. 加热系统间歇泉流动现象初步实验研究. 《核动力工程》.
  201. 黄高峰，曹学武，佟立丽（2012）. 严重事故下裂变产物气溶胶自然沉积现象研究. 《核动力工程》.
  202. 程坤，佟立丽，曹学武（2012）. ITER聚变装置中灰尘带来氢气风险的初步分析. 《核聚变与等离子体物理》.
  203. 莫小锦，庄亚平，佟立丽，曹学武（2012）. AP1000主给水管道断裂事故中PRHR系统冷却能力分析. 《第八届(2012年)北京核学会核应用技术学术交流会论文集》.
  204. 邵舸，佟立丽，曹学武，薛峻峰，吴其方，王勇，严颖第（2012）. 辅助给水系统配置改进的概率安全评价. 《科技导报》.
  205. 莫小锦，佟立丽，曹学武（2012）. AP1000丧失正常给水事故PRHR冷却能力研究. 《科技导报》.
  206. 李京喜，佟立丽，曹学武（2012）. AP1000严重事故下的氢气源项及消氢措施分析. 《科技导报》.
  207. 佟立丽，曹学武（2012）. 非能动安全壳冷却机制安全壳大气净化分析. 《科技导报》.
  208. Hong Gao, Feng Gao, Xianchao Zhao, Jie Chen, Xuewu Cao (2012). Analysis of reactor coolant pump transient performance in primary coolant system during start-up period. Annals of Nuclear Energy.DOI
  209. J.X. Li, Xuewu Cao, Lili Tong, Gaofeng Huang (2012). Radiological consequence evaluation of DBAs with alternative source term method for a Chinese PWR. Nuclear Engineering and Design.DOI
  210. Xue-Wu Cao (2012). The PRHR Cooling Capacity during the Fail of Normal Feedwater Flow Accident for AP1000.
  211. Xue-Wu Cao (2012). Analysis on PRHR System Cooling Capacity During Feedwater System Pipe Break Accident for AP1000.
  212. Xue-Wu Cao (2012). Study on shielded pump system failure analysis method based on Bayesian network.
  213. Xue-Wu Cao (2012). Preliminary analysis of hydrogen risk caused by dust in ITER.
  214. 苑景田，李京喜，曹学武，佟立丽（2011）. 重水堆燃料通道内浮升力引发的间歇式流动现象数值分析. 《核动力工程》.
  215. 陶俊，曹学武（2011）. 堆芯晚期注水对一回路压力的影响分析. 《核动力工程》.
  216. 陶俊，李京喜，佟立丽，曹学武（2011）. 核电厂严重事故下卸压对氢气产生的影响分析. 《原子能科学技术》.
  217. 顾培文，陶俊，曹学武，佟立丽（2011）. LOCA下喷放水流对周围仪表仪器的影响分析. 《核动力工程》.
  218. Jingqi Yuan, J.X. Li, Lili Tong, Xuewu Cao (2011). Thermal hydraulic behaviors during loss of shutdown cooling system at HTS opened under LLDS. Nuclear Engineering and Design.DOI
  219. Tao Jun, Lili Tong, Xuewu Cao (2011). A Study on Natural Circulation Flow under Reactor Cavity Flooding Condition in Advanced PWR. Journal of Power and Energy Systems.DOI
  220. Jie Zou, LI Jingxi, Lili Tong, Xuewu Cao (2011). ICONE19-43410 ANALYSIS OF HYDROGEN MITIGATION IN A SEVERE ACCIDENT. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
  221. Xue-Wu Cao (2011). Analysis of Effect of Late Water Injection on RCS Repressurization.
  222. Xue-Wu Cao (2011). Effect of Depressurization on Hydrogen Generation During Severe Accident in PWR Nuclear Power Plant.
  223. J. Tao, Jing-Xi Li, Li-Li Tong, Xue-Wu Cao (2011). Core cooling in pressurized-water reactor during water injection.DOI
  224. Zhan-Fei Qi, Li-Li Tong, Xue-Wu Cao (2011). Experiment on Geysering Phenomena in Heating System.
  225. 李京喜，黄高峰，曹学武（2010）. 核电厂严重事故下安全壳通风导致放射性后果的快速评价. 《原子能科学技术》.
  226. 袁凯，黄高峰，曹学武，李京喜（2010）. 核电厂全厂断电事故下安全壳响应的计算分析. 《原子能科学技术》.
  227. 佟立丽，曹学武，袁凯，黄高峰（2010）. CANDU堆核电厂全厂断电始发严重事故进程研究. 《原子能科学技术》.
  228. 袁凯，苑景田，邵舸，佟立丽，曹学武（2010）. 出口集管LLOCA始发严重事故分析. 《第六届(2010年)北京核学会核技术应用学术交流会论文集》.
  229. 郑啸宇，黄高峰，曹学武（2010）. 利用可选择源项分析SGTR事故放射性后果的研究. 《核动力工程》.
  230. 侯斌，苑景田，曹学武（2010）. 核电厂一回路系统模拟实验设计与分析. 《第六届(2010年)北京核学会核技术应用学术交流会》.
  231. 李京喜，黄高峰，佟立丽，曹学武（2010）. DVI管线破裂始发严重事故的IVR分析. 《第六届(2010年)北京核学会核技术应用学术交流会论文集》.
  232. 戚展飞，佟立丽，曹学武（2010）. 复杂管段流动压降数值模拟研究. 《核动力工程》.
  233. Hong Gao, Feng Gao, Xianchao Zhao, Jie Chen, Xuewu Cao (2010). Transient flow analysis in reactor coolant pump systems during flow coastdown period. Nuclear Engineering and Design.DOI
  234. Ziqiao Qi, Jinming Li, Lili Tong, Xuewu Cao (2010). Numerical simulation of pressure drop in fuel channel end fitting. Nuclear Engineering and Design.DOI
  235. Zhanfei Qi, Xuewu Cao (2010). Numerical Analysis of Thermal Stratification in Pressurizer Surge Line. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
  236. Jingtian Yuan, Lili Tong, Xuewu Cao (2010). The Thermal-Hydraulics Behavior Analysis Before the CANDU Fuel Channel Dry-Out. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
  237. Gaofeng Huang, Xuewu Cao, LI Jingxi (2010). Preliminary Study of Influence of Severe Accident Mitigation Countermeasures to In-Vessel Release of Fisson Products. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
  238. Xue-Wu Cao (2010). Severe Accident Progression Analysis Induced by LLOCA at Reactor Outlet Header.
  239. Zhan-Fei Qi, Xue-Wu Cao (2010). Numerical Computation of Intermittent Flow in Fuel Channel.
  240. Xue-Wu Cao (2010). Quick Evaluation of Radiological Consequences for Containment Venting in Severe Accident of Nuclear Power Plant.
  241. Xue-Wu Cao (2010). Numerical Simulation of Flow Pressure Drops for Complex Pipe Segment.
  242. Li-Li Tong, K. Yuan, Jing-Tian Yuan, Xue-Wu Cao (2010). Analysis of severe core damage accident progression for the heavy water reactor.DOI
  243. Xue-Wu Cao (2010). Analysis on IVR in Severe Accident Induced by DVI Line Break.
  244. Jing-Tian Yuan, Li-Li Tong, Xue-Wu Cao (2010). Simulation of quenching in horizontal geometry channel.DOI
  245. Xue-Wu Cao (2010). Study on Radiological Consequence Induced by SGTR Accident with Alternative Source Term.
  246. Jing-Tian Yuan, Li-Li Tong, Xue-Wu Cao (2010). Investigation of Intermittent Flow Heat Transfer in Horizontal Fuel Channel.
  247. 黄高峰，李京喜，曹学武（2009）. AP1000小破口失水始发严重事故的源项研究. 《原子能科学技术》.
  248. 黄高峰，佟立丽，曹学武（2009）. AP1000 SGTR始发安全壳旁路型严重事故裂变产物行为分析. 《核动力工程》.
  249. 张琨，佟立丽，曹学武（2009）. 压水堆核电厂自然循环对一回路卸压策略的影响. 《核动力工程》.
  250. 林千，佟立丽，曹学武，KRIVENTSEV Vladimir（2009）. 熔融液滴与水作用细粒化实验研究. 《核动力工程》.
  251. 武铃珺，郭丁情，曹学武（2009）. 压水堆核电厂严重事故下堆腔注水措施研究. 《原子能科学技术》.
  252. 卢放，佟立丽，张琨，曹学武（2009）. 核电厂“半环”运行工况一回路事故进程研究. 《原子能科学技术》.
  253. 黄高峰，佟立丽，邓坚，曹学武（2009）. 核电厂大破口失水事故始发严重事故的源项研究. 《原子能科学技术》.
  254. 林千，佟立丽，曹学武，Alexander VOROBYEV，VladimirK RIVENTSEV（2009）. 熔融金属液滴热细粒化过程研究. 《原子能科学技术》.
  255. 黄高峰，佟立丽，邓坚，曹学武（2009）. 利用可选择源项分析大破口失水事故的放射性后果. 《原子能科学技术》.
  256. 佟立丽，曹学武，郭丁情（2009）. 严重事故下氢气控制系统的优化设计. 《原子能科学技术》.
  257. 曹学武，王喆，张英振（2009）. 运行核电厂事故管理若干问题的探讨. 《核安全》.
  258. Lili Tong, F. Lu, Xuewu Cao, K. Zhang (2009). Thermal hydraulic behaviors during loss of RHR system at mid-loop operation of Chinese 300MWe PWR NPP. Nuclear Engineering and Design.DOI
  259. Gaofeng Huang, Lili Tong, Xuewu Cao (2009). Preliminary Analysis of Effect of the Intentional Depressurization on Fission Product Behavior During TMLB’ Severe Accident. Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications.DOI
  260. Gao-Feng Huang, Li-Li Tong, Jian Deng, Xue-Wu Cao（2009）. 選択的ソースタームを利用して,大規模な口水事故の放射線結果を分析した。【JST・京大機械翻訳】.
  261. Qian Lin, Li-Li Tong, Xue-Wu Cao, A. Vorobyev, V. Kriventsev（2009）. 溶融金属の細粒化プロセスに関する研究【JST・京大機械翻訳】.
  262. Xue-Wu Cao (2009). Source Term in Severe Accident Induced by Large Break Loss of Coolant Accident for Nuclear Power Plant.
  263. Xue-Wu Cao (2009). Study on Accident Progress of Primary System During Mid-loop Operation in Nuclear Power Plant.
  264. Xue-Wu Cao (2009). Radiological Consequences in Large Break Loss of Coolant Accident With Alternative Source Term.
  265. Gao-Feng Huang, Li-Li Tong, Xue-Wu Cao（2009）. AP1000 SGTRの安全性における殻旁路型事故の核分裂生成物挙動解析【JST・京大機械翻訳】.
  266. Gao-Feng Huang, Jing-Xi Li, Li-Li Tong, Xue-Wu Cao (2009). Effect analysis of the intentional depressurization on fission product behavior during TMLB’ severe accident.DOI
  267. Li-Li Tong, Xue-Wu Cao, Jing-Xi Li, Ya-Jun Yang (2009). Model comparisons on molten core-concrete interactions.DOI
  268. Xue-Wu Cao (2009). Effect of Natural Circulation on RCS Depressurization Strategy in PWR NPP.
  269. Xue-Wu Cao (2009). Analysis of Fission Product Behavior in Bypass Containment Severe Accident Induced by SGTR of AP1000.
  270. Xue-Wu Cao (2009). Source Term in Severe Accident Induced by Small Break Loss of Coolant Accident for AP1000.
  271. 杨亚军，曹学武（2008）. 严重事故下堆芯熔融物与混凝土的相互作用. 《原子能科学技术》.
  272. 郭丁情，邓坚，曹学武，佟立丽（2008）. 严重事故下氢气风险及氢气控制系统的初步分析. 《原子能科学技术》.
  273. 苑景田，佟立丽，曹学武，武铃珺（2008）. 压水堆核电厂LOFW始发严重事故下堆腔注水措施影响因素分析. 《原子能科学技术》.
  274. 张琨，曹学武（2008）. 压水堆核电厂高压熔堆严重事故序列分析. 《原子能科学技术》.
  275. 邓坚，曹学武（2008）. 秦山二期核电厂严重事故下安全壳内氢气浓度分布及风险初步分析. 《核动力工程》.
  276. 郭丁情，邓坚，曹学武（2008）. SB-LOCA始发严重事故下压力容器内氢气源项分析. 《核动力工程》.
  277. 邓坚，曹学武（2008）. 氢气催化复合器对核电厂严重事故的缓解效果. 《原子能科学技术》.
  278. 郭丁情，程章华，曹学武（2008）. 蒸汽份额对安全壳内氢气分布的影响. 《原子能科学技术》.
  279. Jian Deng, Xuewu Cao (2008). A study on evaluating a passive autocatalytic recombiner PAR-system in the PWR large-dry containment. Nuclear Engineering and Design.DOI
  280. K. Zhang, Xuewu Cao, Jian Deng, Z. Wang, Licheng Guo, Dingqing Guo, Jingqi Yuan (2008). Evaluation of intentional depressurization strategy in Chinese 600MWe PWR NPP. Nuclear Engineering and Design.DOI
  281. Qian Lin, Zhe Wang, Xuewu Cao (2008). Modeling of Fragmentation of Melt Droplets Triggered by Boiling Effect. Journal of Power and Energy Systems.DOI
  282. Li-Li Tong, Xue-Wu Cao (2008). Methodology for reliability allocation based on fault tree analysis and dualistic contrast.DOI
  283. Xue-Wu Cao (2008). Molten Core-Concrete Interaction Under Severe Accident.
  284. Q. Lin, Li-Li Tong, Xue-Wu Cao, V. Kriventsev (2008). Vapor film collapse triggered by external pressure pulse and the fragmentation of melt droplet in FCIs.DOI
  285. Xue-Wu Cao (2008). Effect of Steam Fraction on Hydrogen Distribution in Containment.
  286. Xue-Wu Cao (2008). Analysis of High-Pressure Core Melt Severe Accidents in PWR Nuclear Power Plant.
  287. Xue-Wu Cao (2008). Hydrogen Removal Effects of Passive Catalytic Recombiners to Mitigate Severe Accident in Nuclear Power Plant.
  288. Xue-Wu Cao (2008). Preliminary Analysis of Hydrogen Distribution and Risk under Severe Accident Conditions for QINSHAN NPP Unit 2 Containment.
  289. 王喆，曹学武（2007）. 快堆燃料组件瞬间完全堵流研究综述. 《原子能科学技术》.
  290. 林千，曹学武（2007）. 燃料与冷却剂相互作用的数值模拟. 《工程热物理学报》.
  291. 程章华，曹学武（2007）. 不同产氢速率对安全壳内氢气分布影响的数值模拟. 《核动力工程》.
  292. 郭连城，曹学武（2007）. 核电厂大LOCA始发严重事故下氢气源项的敏感性分析. 《核动力工程》.
  293. 王喆，曹学武（2007）. 圆管中UO2凝固过程的机理研究. 《核动力工程》.
  294. Jian Deng, Xuewu Cao (2007). Analysis of hot leg natural circulation under station blackout severe accident. Nuclear Science and Techniques.DOI
  295. Z. Wang, Xuewu Cao (2007). Preliminary thermal-hydraulic phenomena investigation during total instantaneous blockage accident for CEFR. Nuclear Engineering and Design.DOI
  296. Qian Lin, Zhe Wang, Xuewu Cao (2007). ICONE15-10103 STUDY ON THE FRAGMENTATION OF MELT DROPLET TRIGGERED BY BOILING EFFECT. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
  297. Deng Jian, Xuewu Cao (2007). ICONE15-10021 EVALUATION OF LATE INTENTIONAL DEPRESSURIZATION AS A SEVERE A ACCIDENT MANAGEMENT STRATEGY. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
  298. Kun Zhang, Xuewu Cao (2007). ICONE15-10037 THE BYPASS PHENOMENON OF SAFETY INJECTION FLOW IN LBLOCA ACCIDENT. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
  299. Jian Deng, Xue-Wu Cao (2007). Hydrogen and steam distribution following a small-break LOCA in large dry containment.DOI
  300. Q. Lin, Xue-Wu Cao (2007). Simulation of the mixing process in FCIs with hydrodynamic fragmentation model.DOI
  301. Xue-Wu Cao (2007). Sensitivity Analysis of Hydrogen Source during Severe Accident Induced by Large LOCA for NPP.
  302. Xue-Wu Cao (2007). Review of Study on Total Instantaneous Blockage Accident in Fast Reactor.
  303. Q. Lin, Xue-Wu Cao (2007). Study on thermal fragmentation mechanisms of melt droplets.
  304. Xue-Wu Cao (2007). Study on Mechanism of UO_2 Freezing in Tube.
  305. Kun Zhang, Xuewu Cao (2007). Analysis of intentional primary depressurization strategy in LOFW accident.
  306. J. Tao, Xuewu Cao (2007). Study on in-vessel retention strategy in 300MW PWR of China.
  307. 纪段，曹学武，车济尧（2006）. 稳压器卸压阀卸压效果研究. 《核动力工程》.
  308. 纪段，曹学武（2006）. 压水堆一回路卸压措施影响因素研究. 《原子能科学技术》.
  309. Deng Jian, Xuewu Cao (2006). Analysis of Potential Hydrogen Risk in the PWR Containment.DOI
  310. Qian Lin, Xuewu Cao (2006). Development of a Thermal Fragmentation Model for Single Metal Droplet in FCIs.DOI
  311. Zhe Wang, Xuewu Cao (2006). Study on Total Instantaneous Blockage Accident for CEFR.DOI
  312. Kun Zhang, Xuewu Cao (2006). Study on the Accidental Rupture of Hot Leg or Surge Line in SBO Accident.DOI
  313. Xue-Wu Cao (2006). Study on Primary Coolant System Depressurization Effect Factor in Pressurized Water Reactor.
  314. Kun Zhang, Xuewu Cao (2006). Preliminary study on the development of chinese PWR SAMG.
  315. Kunyi Zhang, Xuewu Cao, Ji-Gang Che (2006). Study on severe accident mitigation measures for the development of PWR SAMG.DOI
  316. 车济尧，曹学武（2005）. 秦山一期核电站未能紧急停堆的预期瞬变导致堆芯熔化的进程及事故缓解措施研究. 《核动力工程》.
  317. 陈兆兵，曹学武（2005）. 核电系统的故障树可靠性定量分析数字仿真. 《计算机仿真》.
  318. Xue-Wu Cao (2005). Studyon Severe Core Damage Progression Induced by Anticipated Transients without Scram and Its Mitigation in Qinshan NPP Unit1.
  319. Xue-Wu Cao (2005). Digital Simulation of Reliability Qualitative Analysis of Fault Tree in Nuclear Power System.
  320. 许以全，苏云，曹学武（2004）. 秦山一期核电站SGTR导致堆芯熔化进程及事故缓解措施的研究. 《核动力工程》.
  321. 许以全，车济尧，曹学武（2004）. 秦山一期核电站堆芯熔化进程以及缓解措施的研究. 《21世纪初辐射防护论坛第三次会议暨21世纪初核安全论坛第一次会议》.
  322. 许以全，车济尧，苏云，曹学武（2004）. 秦山一期核电站小破口冷却剂丧失初因严重事故以及缓解措施的研究. 《核动力工程》.
  323. 陈东海，曹学武（2004）. 高温小球在冷却剂中运动阻力特性的研究. 《核动力工程》.
  324. 佟立丽，曹学武（2004）. 核电技术自主化发展中安全保障技术的探讨. 《核安全》.
  325. 曹学武，苏云，刘宝亭（2004）. 严重事故预防与缓解措施. 《21世纪初辐射防护论坛第三次会议暨21世纪初核安全论坛第一次会议》.
  326. Zhi Shang, Ruichang Yang, Xuewu Cao, Yanhua Yang (2004). An investigation of two-phase flow instability using wavelet signal extraction technique. Nuclear Engineering and Design.DOI
  327. Xue-Wu Cao (2004). An Experimental Investigation of Drag Characteristic of A Hot Particle Moving in Coolant Liquid.
  328. Xue-Wu Cao (2004). Study on the Progression of Severe Core Damage Induced by SGTR and Mitigation Measures for QINSHAN NPP Unit 1.
  329. 苏云，许以全，曹学武，徐济鋆（2003）. SCDAP/RELAP5程序结构及严重事故有关的模型概述. 《核动力工程》.
  330. 曹学武，飞田吉春（2003）. 核反应堆严重事故中燃料与冷却剂相互作用粗混合过程的数值模型验证. 《核动力工程》.
  331. 曹学武（2003）. 日本商用快中子增殖堆安全研究. 《全国放射性流出物和环境监测与评价研讨会》.
  332. 苏云，许以全，曹学武，徐济鋆（2003）. 最佳估算程序在安全分析中的应用综述. 《全国放射性流出物和环境监测与评价研讨会论文汇编》.
  333. Xue-Wu Cao (2003). Verification of a Drag Model for Simulation of Premixing Stage in Fuel Coolant Interaction.
  334. Xuewu Cao, Y. Tobita, S. Kondo (2002). A Thermal Fragmentation Model Induced by Surface Solidification.DOI
  335. Xuewu Cao, Y. Tobita (2001). Drag Correlations for a Hot Particle/Droplet with Vapor Film.DOI
  336. Xuewu Cao, R. Hajima, K. Furuta, S. Kondo (2000). A Numerical Analysis of Molten Metal Drop and Coolant Interaction.DOI
  337. 曹学武，李兆桓（1991）. 秦山核电站燃料元件考验回路PSA(英文). 《中国核科技报告》.

预印本

  1. Xue‐Song Bai, Lili Tong, Xuewu Cao (2025). Non-Equilibrium Melting Characteristics of Boron Carbide–Stainless Steel Eutectic Reaction Under Rapid Heating Conditions. SSRN Electronic Journal.DOI

书籍章节

  1. Peizheng Hu, Zhen Xu, Junlong Wang, Lili Tong, Xuewu Cao (2023). Experimental Study on Aerosol Removal Effected by Spray Characterization. Springer proceedings in physics.DOI
  2. Zhenyu Zou, Lili Tong, Xuewu Cao (2023). Sodium Spray Fire Analysis with Combustion Space Multi-node Model for Sodium-Cooled Fast Reactor. Springer proceedings in physics.DOI
  3. Zhichao Gao, Lili Tong, Xuewu Cao (2023). Experiments of Polydisperse Aerosol Transport Progress in Horizontal and Vertical Pipes. Springer proceedings in physics.DOI

研究方向

核科学技术物理学

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