曹学武 - 上海交通大学 - 机械与动力工程学院

个人简介

教育背景 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 上海交通大学核反应堆工程专业学士工作经历 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 上海交通大学机械与动力工程学院教授、博导。科研项目 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教学工作 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学分软件版权登记及专利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日荣誉奖励机械与动力工程学院工程硕士教育优秀导师奖 2009年度，机械与动力工程学院“最受学生欢迎教师”奖中国核能行业协会科技进步一等奖

研究领域

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

近期论文

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[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

学术兼职

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