1999 日本东京大学核反应堆工程专业 博士
1988 中国原子能科学研究院核反应堆工程专业 硕士
1983 BETVLCTOR伟德在线登录平台核反应堆工程专业 学士

1983 中国工程物理研究院西南核物理与化学研究所；
1988 中国原子能科学研究院 工程师/副研究员；
1999 日本核燃料循环开发研究所大洗工学中心；
2002 BETVLCTOR伟德在线登录平台 教授、博导。

核反应堆安全分析及评价
反应堆严重事故
概率安全评价
核反应堆热工水力
聚变堆热工水力及安全

2019-2024，主持科技部重点研发计划课题
2015-2019，主持国家重大专项项目
2014-2018，主持国际热核聚变实验堆（ITER）计划专项项目
2014-2017，主持国家自然科学基金面上项目
2011-2013，主持国家自然科学基金面上项目
2009-2013，主持国家科技部973计划课题
2010-2012，主持教育部博士点基金
2010-2013，主持国际热核聚变实验堆（ITER）计划专项课题
2007-2008，主持国家自然科学基金中俄合作基金项目
2006-2008，主持国家自然科学基金面上项目

[1] D Wand, L Tong *, X Cao. Numerical study on the influence of steam condensation on hydrogen distribution in local compartments. Annals of Nuclear Energy. 121 (2018) 468-478.
[2] L Tong*, X Zhou, X Cao. Ultimate pressure bearing capacity analysis for the prestressed concrete containment. Annals of Nuclear Energy. 121 (2018) 582-593
[3] C.P, L.L.Tong, X.W.Cao. A hydrodynamic fragmentation model based on boundary layer stripping. Annals of Nuclear Energy 80 (2015) 95-100.
[4] Y.B.Li, X.W. Cao*. Strategy evaluation for fire spray system on Advanced Passive PWR Severe Accident Management Guideline. Progress in Nuclear Energy 85 (2015) 319-324.
[5] J.B.Chen, X.W. Cao*. Experimental investigation of effective parameters on geyser periodicity in a vertical heated system. Experimental Thermal and Fluid Science 68(2015) 163–176.
[6] J.B.Chen, X.W. Cao*. Study on intermittent flow behavior in a vertical channel under low-pressure condition. Journal of Nuclear Science and Technology 52(1) (2015) 131–142.
[7] G.F.Huang, L.L.Tong, X.W.Cao*. Study on Mitigation of Ex-vessel Release of Fission Products in Severe Accidents of PWR. Progress in Nuclear Energy 2015, 78: 56-64.
[8] Y.B.Li, L.L.Tong, X.W.Cao*. In-vessel retention coolability evaluation for Chinese improved 1000 MWe PWR. Annals of Nuclear Energy. 2015, 76: 343–349.
[9] X.M.You, L.L.Tong, X.W.Cao. Preliminary experimental study of liquid lithium water interaction. Fusion Engineering and Design, doi:10.1016/j.fusengdes.2015.02.057.
[10] X.M.You, X.W. Cao*. Study of liquid lithium coolant interaction based on BP neural network optimized by genetic algorithm. Journal of Fusion Energy 34 (3)(2015) 671-678.
[11] L.L.Tong, G.F. Huang, X.W.Cao∗. Simulation of fission products behavior in severe accidents for advanced passive PWR. Annals of Nuclear Energy 2015,76 : 493–503
[12] L.L.Tong, J.B. Chen, X.W. Cao∗. Visualization experiments on the geyser boiling-induced instability in vertical circular tube at low-pressures. Annals of Nuclear Energy 2015, 77: 487-497
[13] L.L.Tong, R.Duan, X.W.Cao∗. Seismic analysis of RCS with finite element model for advanced PWR. Progress in Nuclear Energy 2015, 79: 142-149.
[14] L.L.Tong, J. Zou, X.W.Cao∗. Analysis on hydrogen risk mitigation in severe accidents for Pressurized Heavy Water Reactor. Progress in Nuclear Energy. 2015,80:128-135
[15] L.Q.Hou, L.L.Tong, X.W. Cao∗. Dust migration simulation during loss of vacuum accident. Journal of Fusion Engineering. DOI: 10.1007/s10894-014-9842-y
[16] K.Yuan, L.L.Tong, X.W.Cao*. Evaluation of Containment Venting Strategy via VFS path for advanced passive PWR NPP. Progress in Nuclear Energy 2014, 73: 102-106
[17] J.Zou, L.L.Tong, X.W.Cao*. Assessment of passive residual heat removal system cooling capacity. Progress in Nuclear Energy 2014, 70:159-166
[18] K.Yuan, L.L.Tong, X.W.Cao*. Analysis on Containment Depressurization under Severe Accidents for a Chinese 1000MWe NPP. Progress in Nuclear Energy 2013, 65:8-14
[19] J.X.Li, X.W.Cao∗. Radiological consequence evaluation of DBAs with alternative source term method for a Chinese PWR. Nuclear Engineering and Design 2012,250:260-266.
[20] J.T.Yuan, J.X.Li, L.L.Tong, X.W. Cao∗.Thermal hydraulic behaviors during loss of shutdown cooling system at HTS opened under LLDS. Nuclear Engineering and Design 2011,241: 2093-2098.
[21] J.Deng, X.W Cao∗. A study on implementing a passive autocatalytic recombiner PAR-system in the large-dry containment,Nuclear Engineering and Design 2008,238(7):2554–2560.
[22] G.F.Huang, J.X.Li, L.L.Tong, X.W.Cao∗. Analysis of effect of the intentional depressurization on fission product behavior during TMLB’severe accident. Nuclear Science and Techniques，2009,20(6) :373-379.
[21] 侯丽强, 佟立丽*, 曹学武. 聚变装置失真空事故下灰尘迁移的数值研究. 原子能科学技术, 2014, 48: 369-375
[22] 邹杰, 佟立丽, 曹学武. 典型严重事故非能动安全壳冷却系统效果分析. 原子能科学技术, 2014, 48: 362-368
[23] 段蓉，佟立丽，曹学武*.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. 2014, 48(10):1836-1843
[24] 戚展飞，陈金波，佟立丽，曹学武*. 加热系统间歇泉流动机理与模型研究. 原子能科学技术.2013,47(4):546-551
[25] 戚展飞，陈金波，佟立丽，曹学武. 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.2013,34(2):9-15
[26] 邵舸，佟立丽，曹学武. 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.2013,47(7):1187-1191
[27] 李若晴，佟立丽，曹学武. 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. 2013,33(2):175-179
[28] 邹杰，佟立丽，曹学武，江宇，郝禄禄，仇苏辰，刘力. 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.2013,34.S1:47-50

1. 核电厂系统与设备，本科生，36学时，2学分
2. 核能及核安全，本科生，16学时，1学分
3. 严重事故现象及管理，研究生，48学时，3学分

基于外置喷淋的核反应堆安全壳冷却模拟系统及方法 ZL 2016 1 0165092.8
熔融物中频感应高温加热装置 ZL 201510012171.0
高温熔融物释放装置 ZL 201510012196.0
基于序列的堆芯损伤评价系统v1.0 2016SR263580
反应堆主泵故障诊断与监测软件V1.2，2013SR053469.2013年6月1日

核学会核安全分会理事
核学会船用核动力分会理事
核反应堆系统设计技术重点实验室学术委员会委员

BETVLCTOR伟德在线登录平台工程硕士教育优秀导师奖
2009年度，BETVLCTOR伟德在线登录平台“最受学生欢迎教师”奖
中国核能行业协会科技进步一等奖