1999    日本東京大學(xué)核反應(yīng)堆工程專業(yè)    博士
1988    中國(guó)原子能科學(xué)研究院核反應(yīng)堆工程專業(yè)    碩士
1983    上海交通大學(xué)核反應(yīng)堆工程專業(yè)    學(xué)士

1983 中國(guó)工程物理研究院西南核物理與化學(xué)研究所；
1988 中國(guó)原子能科學(xué)研究院 工程師/副研究員；
1999 日本核燃料循環(huán)開發(fā)研究所大洗工學(xué)中心；
2002 上海交通大學(xué)機(jī)械與動(dòng)力工程學(xué)院 教授、博導(dǎo)。

核反應(yīng)堆安全分析及評(píng)價(jià)
反應(yīng)堆嚴(yán)重事故
概率安全評(píng)價(jià)
核反應(yīng)堆熱工水力
聚變堆熱工水力及安全

核學(xué)會(huì)核安全分會(huì)理事
核學(xué)會(huì)船用核動(dòng)力分會(huì)理事
核反應(yīng)堆系統(tǒng)設(shè)計(jì)技術(shù)重點(diǎn)實(shí)驗(yàn)室學(xué)術(shù)委員會(huì)委員

2019-2024，主持科技部重點(diǎn)研發(fā)計(jì)劃課題
2015-2019，主持國(guó)家重大專項(xiàng)項(xiàng)目
2014-2018，主持國(guó)際熱核聚變實(shí)驗(yàn)堆（ITER）計(jì)劃專項(xiàng)項(xiàng)目
2014-2017，主持國(guó)家自然科學(xué)基金面上項(xiàng)目
2011-2013，主持國(guó)家自然科學(xué)基金面上項(xiàng)目
2009-2013，主持國(guó)家科技部973計(jì)劃課題
2010-2012，主持教育部博士點(diǎn)基金
2010-2013，主持國(guó)際熱核聚變實(shí)驗(yàn)堆（ITER）計(jì)劃專項(xiàng)課題
2007-2008，主持國(guó)家自然科學(xué)基金中俄合作基金項(xiàng)目
2006-2008，主持國(guó)家自然科學(xué)基金面上項(xiàng)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] 侯麗強(qiáng), 佟立麗*, 曹學(xué)武. 聚變裝置失真空事故下灰塵遷移的數(shù)值研究. 原子能科學(xué)技術(shù), 2014, 48: 369-375
[22] 鄒杰, 佟立麗, 曹學(xué)武. 典型嚴(yán)重事故非能動(dòng)安全殼冷卻系統(tǒng)效果分析. 原子能科學(xué)技術(shù), 2014, 48: 362-368
[23] 段蓉，佟立麗，曹學(xué)武*.先進(jìn)壓水堆一回路地震反應(yīng)譜分析及參數(shù)敏感性研究. 原子能科學(xué)技術(shù). 2014, 48(10):1836-1843
[24] 戚展飛，陳金波，佟立麗，曹學(xué)武*. 加熱系統(tǒng)間歇泉流動(dòng)機(jī)理與模型研究. 原子能科學(xué)技術(shù).2013,47(4):546-551
[25] 戚展飛，陳金波，佟立麗，曹學(xué)武. 加熱系統(tǒng)間歇泉流動(dòng)特征及影響因素實(shí)驗(yàn)研究，核動(dòng)力工程.2013,34(2):9-15
[26] 邵舸，佟立麗，曹學(xué)武. 反應(yīng)堆主回路卸壓對(duì)壓力容器外裂變產(chǎn)物釋放的影響分析. 原子能科學(xué)技術(shù).2013,47(7):1187-1191
[27] 李若晴，佟立麗，曹學(xué)武. ITER第一壁冷卻劑管道斷裂事故熱工水力初步分析，核聚變與等離子體物理. 2013,33(2):175-179
[28] 鄒杰，佟立麗，曹學(xué)武，江宇，郝祿祿，仇蘇辰，劉力. 百萬千瓦級(jí)壓水堆嚴(yán)重事故下氫氣源項(xiàng)及氫氣控制有效性分析. 核動(dòng)力工程.2013,34.S1:47-50

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