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王明军
发布时间：2018-07-14 16:25:56 点击：

王明军，男，1988年8月生，工学博士，副教授。主要研究方向为核反应堆热工水力，安全分析及CFD数值计算等。2015年获得西安交通大学核科学与技术专业博士学位，2013年至2015年在美国密歇根大学核工程系博士联合培养2年。主持或参与了国家自然科学基金、十三五国防预研、原总装预研、科技部重点研发计划、博士后一等基金、法国电力EDF、军工及企业横向课题多项。曾获得了教育部技术发明一等奖（8/8），发表学术论文40余篇，其中SCI文章30篇，申请发明专利10项，曾担任国际核工程大会(ICONE)、中日三校核科学与技术研讨会等国际会议的分会主席，是《Annals of Nuclear Energy》、《Progress in Nuclear Energy》及《Experimental Thermal and Fluid Science》等多个核能国际期刊的审稿人。

讲授课程：

核反应堆热工安全分析计算，本科生课程
核反应堆热工分析，本科生课程
核反应堆热工数值分析，研究生课程

科研奖励：

1. 先进核动力系统热工水力三维全尺寸动态模拟技术与系统，技术发明奖一等奖，教育部，2016.11（第8完成人）

部分期刊论文：

Mingjun Wang, Leyuan Bai, Lianfa Wang, Suizheng Qiu, Wenxi Tian, G.H. Su. Thermal hydraulic and stress coupling analysis for AP1000 Pressurized Thermal Shock (PTS) study under SBLOCA scenario [J], Applied Thermal Engineering, 2017 , 122: 158-170.
Mingjun Wang, Di Liu, Yan Xiang, Shijie Cui, G.H. Su, Suizheng Qiu, Wenxi Tian. Experimental study of the helium flow characteristics in pebble-bed under the condition of CFETR's blanket module [J]. Progress in Nuclear Energy, 2017, 100: 283-291.
Mingjun Wang, Qiaolin Zuo, Hao Yu, Wenxi Tian, G. H. Su, Suizheng Qiu. Multiscale Thermal Hydraulic Study under the Inadvertent Safety Injection System Operation Scenario of Typical Pressurized Water Reactor [J]. Science & Technology of Nuclear Installations, 2017, 2017: 1-15.
Mingjun Wang, Lianfa Wang, Jianping Jing, Xinli Gao, Suizheng Qiu, Wenxi Tian, G.H. Su. Study on the reactor core barrel instantaneous characteristics in case of Loss of Coolant Accident (LOCA) scenarios for loop-type PWR [J]. Nuclear Engineering and Design, 2017, 324: 93-102.
Mingjun Wang, Yan Xiang, Shijie Cui, Di Liu, Wenxi Tian, Dalin Zhang, SuizhengQiu, G. H. Su. Numerical study on the purge gas flow and heat transfer characteristics in helium cooled solid breeder blanket of CFETR [J]. Progress in Nuclear Energy, 2018, 105:114-123.
Mingjun Wang, Annalisa Manera, Victor Petrov, et al. Passive Decay Heat Removal (DHR) System Design for the Integral Inherent Safety Light Water Reactor (I2S-LWR)[J]. Annals of Nuclear Energy I2S-LWR Special Issue, 2017.
Mingjun Wang, Annalisa Manera, Matthew J. Memmott, et al. Preliminary Design of the I2S-LWR Containment Syste[J]. Annals of Nuclear Energy I2S-LWR Special Issue, 2017.
Mingjun Wang, Annalisa Manera, Suizheng Qiu, Guanghui Su. Ammonia-Water mixture Property Code (AWProC) development, verification and Kalina cycle design for nuclear power plant [J]. Progress in Nuclear Energy, 2016, 91: 26-37.
Mingjun Wang, Dalin Zhang, Suizheng Qiu, Wenxi Tian, Guanghui Su. Accident analyses for china pressurizer reactor with an innovative conceptual design of passive residual heat removal system [J]. Nuclear Engineering and Design, 2014, 272: 45-52.
Mingjun Wang, Suizheng Qiu, Guanghui Su, Wenxi Tian. Research on the leak-rate characteristics of leak-before-break (LBB) in pressurized water reactor (PWR) [J]. Applied Thermal Engineering, 2014, 62: 133-140.
Mingjun Wang, Wenxi Tian, Suizheng Qiu, Guanghui Su, Yapei Zhang. An evaluation of designed passive Core Makeup Tank (CMT) for China Pressurized Reactor (CPR1000) [J]. Annals of Nuclear Energy, 2013, 56: 81-86.
Mingjun Wang, Suizheng Qiu, Guanghui Su, Wenxi Tian. Preliminary study of parameter uncertainty influence of pressurized water reactor core design [J]. Progress in Nuclear Energy, 2013, 68: 200-209.
Mingjun Wang, Suizheng Qiu, Wenxi Tian, Guanghui Su, Yapei Zhang. The comparison of designed water-cooled and air-cooled passive residual heat removal system for 300 MWe nuclear power plant during the feed-water line break scenario [J]. Annals of Nuclear Energy, 2013, 57: 164-172.
Mingjun Wang, Hao Zhao, Yapei Zhang, Guanghui Su, Wenxi Tian, Suizheng Qiu. Research on the Designed Emergency Passive Residual Heat Removal System During the Station Blackout Scenario for CPR1000 [J]. Annals of Nuclear Energy, 2012, 45: 86-93.
Mingjun Wang, Annalisa Manera, Victor Petrov, Suizheng Qiu, Wenxi Tian, G. H. Su. Numerical Study of Integral Inherently Safe Light Water Reactor in Case of Inadvertent DHR Operation Based on the Multiscale Method. Nuclear Technology, 2018. (Accepted)
Longze Li, Mingjun Wang, Wenxi Tian, Guanghui Su, Suizheng Qiu. Severe Accident Analysis for Typical PWR using the MELCOR code [J]. Progress in Nuclear Energy, 2014, 71: 30-38.
Tangtao Feng, Mingjun Wang, Ping Song, Wenxi Tian, G.H. Su, Suizheng Qiu, Thermal hydraulic characteristics analysis of direct residual heat removal system for China pressurized reactor[J]. Progress in Nuclear Energy, 2016, 93: 231-237.
Zhenhui Ma, Yuzhou Lu, Ronghua Chen, Hang Xiao, Mingjun Wang, G.H. Su, Suizheng Qiu, Wenxi Tian. Study on the hydrogen risk in venturi scrubber filter of filtered containment venting system under PWR severe accident. Nuclear Engineering and Design, 2018, 327: 61-69.
Jing Chen, Dalin Zhang, Ping Song, Xinan Wang, Shibao Wang, Yu Liang, Suizheng Qiu, Yapei Zhang, Mingjun Wang, G.H. Su. CFD investigation on thermal-hydraulic behaviors of a wire-wrapped fuel subassembly for sodium-cooled fast reactor. Annals of Nuclear Energy, 2018, 113: 256-269.
Memmott, M.J., Manera, A., Boyack, J., Pacheco, S., Wang, M., Petrovic, B., "The primary reactor coolant system concept of the integral, inherently-safe light water reactor", Annals of Nuclear Energy, 2016, 100(1): 53-67.
Andrew M. Ward, Mingjun Wang, Matthew D. Neumann, Matthew Memmott, Thomas J. Downar, David Salazar, Fausto Franceschini, Thomas J. Downar. Simulated Transient Behavior of the I2S Reactor Design[J]. Annals of Nuclear Energy I2S-LWR Special Issue, 2017.
Yangbin Deng, Yingwei Wu, Bowen Qiu, Dalin Zhang, Mingjun Wang, Wenxi Tian, Suizheng Qiu, G.H. Su. Development of a new Pellet-Clad Mechanical Interaction (PCMI) model and its application in ATFs. Annals of Nuclear Energy, 2017, 104:146-156.
Jing Zhang, Ronghua Chen, Mingjun Wang, Wenxi Tian, Guanghui Su, Suizheng Qiu. Prediction of LBB leakage for various conditions by genetic neural network and genetic algorithms[J]. Nuclear Engineering and Design, 2017, 325: 33-43.
Jing Zhang, Ronghua Chen, Mingjun Wang, Wenxi Tian, Guanghui Su, Suizheng Qiu. A code development for leak before break (LBB) leakage from supercritical to subcritical conditions[J]. Progress in Nuclear Energy, 2018, 103: 217-228.
Rulei Sun, Dalin Zhang, Yu Liang, Mingjun Wang, Wenxi Tian, Suizheng Qiu, Guanghui Su. Development of a subchannel analysis code for SFR wire-wrapped fuel assemblies. Progress in Nuclear Energy, 2018, online.
Yongzheng Chen, Y. W. Wu, M. J. Wang, Y. P. Zhang, B.Tan, D. L. Zhang, W. X. Tian, S. Z. Qiu, G. H. Su. Development of a multi-compartment containment code for advanced PWR plant, Nuclear Engineering and Design, 2018, 334: 75-89.
Shibao Wang, Dalin Zhang, Ping Song, Yapei Zhang, Mingjun Wang, Yingwei Wu, Suizheng Qiu. Validation of a methodology for thermal stratification analysis in sodium-cooled fast reactors. International Journal of Energy Research. 2018.
王明军,张亚培,田文喜等. 主给水管道破口尺寸对CPR1000二次侧非能动应急热阱事故缓解能力影响研究[J]. 原子能科学技术, 2012, 46(7): 821-826.
王明军,苏亚丽,秋穗正等. LBB泄漏率计算与热力学非平衡效应影响评估[J]. 原子能科学技术, 2013, 47(8): 1330-335.
王明军,张亚培,田文喜等. CPR1000二次侧非能动应急热阱设计与事故缓解能力分析[J]. 原子能科学技术, 2012, 46(3): 321-327.
李龙泽,王明军,田文喜等. CPR1000全厂断电叠加蒸汽发生器安全阀误开启事故引起的严重事故分析[J]. 原子能科学技术, 2014, 48: 1020-1025 (EI: 20142817936341).
左巧林, 秋穗正, 王明军. 恰希玛核电厂压力容器各关键部位在PTS瞬态下的温度场研究. 原子能科学技术, 2016, 50: 829-834.

部分会议论文：
Mingjun Wang, Yapei Zhang, Wenxi Tian, et al. Emergency Passive Safety System (EPSS) Design for China Pressurized Reactor (CPR1000)[C]. NUSSA, Beijing, China, Sep.7-8, 2012.
Mingjun Wang, Suizheng Qiu, Wenxi Tian, et al. The Improved Design of Passive Residual Heat Removal System and Steady state/Transient Analysis for China Pressurizer Reactor [C]. Proceedings of ICAPP 2013 Jeju Island, Korea, Apr.14-18, 2013.
Mingjun Wang, Annalisa Manera, Suizheng Qiu. Development of an Ammonia-water mixture property code (AWProC) for Kalina cycle[C]. ANS 2014 annual meeting- ATH’14. Reno, NV, US, June 15-19, 2014 (EI: 20144400145936).
Mingjun Wang, Annalisa Manera, Matthew J. Memmott, et al. Passive Decay Heat Removal (DHR) System Design for the Integral Inherent Safety Light Water Reactor (I2S-LWR)[C]. NURETH 16, Chicago, US, Aug.30-Sep.4, 2015.
Mingjun Wang, Annalisa Manera, Matthew J. Memmott, et al. Preliminary Design of the I2S-LWR Containment System[C]. NURETH 16, Chicago, US, Aug.30-Sep.4, 2015.
Mingjun Wang, Annalisa Manera, Suizheng Qiu, Victor Petrov, Wenxi Tian, G. H. Su. Study on the lower head mixing characteristics in case of inadvertent Decay Heat Removal (DHR) system operation for I2S-LWR[C]. ISSNP2016, September 26-28, Chengdu, China.
Longze Li, Mingjun Wang, Wenxi Tian, et al. The Severe Accident Analysis of CPR1000 Based on MELCOR Code[C]. The 21st International Conference on Nuclear Engineering, Chengdu, China, Jul.29-Aug.2, 2013.
Eric Welch, Annalisa Manera, Matt Memmott, Paolo Ferroni, Mingjun Wang, John C. Lee. Preliminary Safety Considerations for the Integral Inherently Safe Light Water Reactor (I2S-LWR)[C]. ANS winter meeting, Anaheim, CA, US, Nov.9-13, 2014.
Mingjun Wang, Yi Fei, Wenxi Tian, et al. Numerical study on the coolant mixing phenomenon in a T junction using CFD method. The 10thJoint International Symposium on Nuclear Science and Technology. 2017, Nov.22-24, Xi’an, China.
Xinan Wang, Dalin Zhang, Mingjun Wang, Wenxi Tian, Suizheng Qiu, Guanghui Su, A Mesh Mapping Method for MCNP and FLUENT Coupling Simulation. ANS 2017 annual meeting, Washington, DC, Oct. 29 - Nov. 2, 2017.
王明军，冯唐涛，秋穗正，田文喜，苏光辉. 一体化固有安全大型轻水堆（I2S-LWR）安全壳三维冷凝特性研究. 中核核反应堆热工水力技术重点实验室2016年度学术交流会议, 2016, 11月16-18日，成都，中国.
冯唐涛，张大林，田文喜，王明军，苏光辉，秋穗正. 基于耦合程序的流体瞬变流动水锤现象分析. 中核核反应堆热工水力技术重点实验室2016年度学术交流会议, 2016, 11月16-18日，成都，中国.
王明军, 田文喜. 数值反应堆技术中的CFD方法, 核能发电技术创新高峰论坛, 2018, 6月4-7日，福州，中国.

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王明军 发布时间：2018-07-14 16:25:56 点击：_showDynClicks("wbnews", 1503526830, 1330)

王明军
发布时间：2018-07-14 16:25:56 点击：