教育背景
博士 2005.01 清华大学 核能科学与工程
硕士 2001.07 清华大学 核能科学与工程
学士 1999.07 清华大学 工程物理专业
工作履历
2005.03 – 2011.12 清华大学核能与新能源技术研究院 助理研究员
2011.12 – 至今 清华大学核能与新能源技术研究院 副研究员
学术兼职
201705 - 201910 全国反应堆热工流体专业委员会青年工作委员会 副主任委员
研究领域
主要从事先进反应堆（大型先进压水堆、高温气冷堆、低温供热堆）的相关热工设计和安全分析方面的工作，并进行热工安全分析程序的数值开发和应用研究。作为子课题负责人或主要参与者参加了“大型先进压水堆及高温气冷堆核电站科技重大专项”多个课题的研究工作。
研究概况
2012 –2022 参与全自然循环反应堆/主回路系统设计 企业合作
2019 –2021 负责先进核能特征统计优化软件开发 企业合作
2019 –2021 参与领创基金项目 企业合作
2010 –2019 参与大型先进压水堆及高温气冷堆核电站科技重大专项”高温气冷堆物理热工规律研究(ZX06908-002) 国家重大科技专项
2011 –2014 参与液滴在高速运动氦气中的喷放及传输特性研究 清华大学自主科研计划
2011 –2011 主持台风、暴雨灾害对核电站土建工程影响与相应防灾防损措施 企业合作
2009 –2014 参与"大型先进压水堆及高温气冷堆核电站科技重大专项”先进压水堆"反应堆堆芯及安全分析关键技术研究"(2011ZX06004) 国家重大科技专项
学术成果
已发表在相关专业领域的学术期刊或国内外科技会议中发表论文40余篇，代表性的论文如下：
Zixuan Wang; Haipeng Xu; Yan Wang*. Uncertainty and Sensitivity Analysis of Core Flow Distribution Optimization Using Monte-Carlo Method and Wilks' Formula. Progress in Nuclear Energy, 2025, 186(105828)
2 Zixuan Wang; Haipeng Xu; Yan Wang*. Core flow distribution optimization of a natural circulation reactor using genetic algorithm, simulated annealing and characteristic statistic algorithm. Progress in Nuclear Energy, 2023, 165(104904)
3 Zixuan Wang; Yan Wang*; Haipeng Xu; Heng Xie. Application of Simulated Annealing Algorithm in Core Flow Distribution Optimization. Energies, 2022, 15(21): 15218242
4 Xu Haipeng; Wang Yan*. A preliminary analysis on optimization of core flow distribution Progress in Nuclear Energy, 2022, 146(104147)
5 Zhipeng Chen; Yan Wang; Yanhua Zheng. Discussion on the accident behavior and accident management of the HTGR. Nuclear Engineering and Design, 2020, 360(110497)
6 Zeguang Li; Yan Wang; Jing Zhao; Zhihong Liu. Development of the universe based geometry criticality search capability in RMC and analysis of NHR200-II reactor. Annals of Nuclear Energy, 2019, 12, 134: 401-413.
7 Wang Yan*; Yang yanning. Study on containment pressure response with passive containment cooling system performance under design basis accident . Progress in Nuclear Energy, 2017, 94: 22-35
8 Wang Yan*; Shi Lei; Zheng Yanhua. Analysis of Precooling Injection Transient of Steam Generator for High Temperature Gas Cooled Reactor. Science and Technology of Nuclear Installations, 2017, 2017: 0-8521410
9 Wang Yan*; Zheng Yanhua; Li Fu; Shi Lei. Analysis on blow-down transient in water ingress accident of high temperature gas-cooled reactor. Nuclear Engineering and Design, 2014, 271: 404-410.
10 Wang Yan*. Study on pressure relief system design for high temperature gas cooled reactor. Progress in Nuclear Energy, 2014, 77: 344-351
11 徐海鹏; 王岩*; 解衡. 自然循环反应堆流量分配优化研究. 原子能科学技术, 2020, 54(7): 1153-1160
12 王岩*; 解衡; 谢菲. 自然循环反应堆NHR-200Ⅱ失水事故初步研究. 原子能科学技术, 2020, 54(5): 769-775
13 解衡; 王岩; 谢菲. NHR-200Ⅱ型低温供热堆安全特性. 原子能科学技术, 2019, 10(10): 1-7
14 Li, Zeguang; Lang, Minggang; Zhao, Jing; Wang, Yan; Liu, Zhihong; Wei chunlin. Reactor physics analysis of NHR200-II heating reactor using RMC Monte Carlo code. International Conference on Nuclear Engineering, Proceedings, ICONE, May 18, 2019
15 Ge Feng; Wang Yan. Study of inlet resistance arrangement for optimizing core flow distribution. 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, Xi an, 2017-9
16 Wang yan; Shi lei; Zheng yanhua Influence of protective actions on ingress-water mass in Steam generator tube rupture of HTGR. 8th Innternational Topical Meeting on High Temperature Reaactor Technology(HTR2016), Lasvagas NV USA, 2016-11-5 to 2016-11-10
17 Wang dingqu; Wang yan; Li songyang. Analysis of flashing and slow descending phenomenon in ring coelom of integrated reactor during LOCA. 24th International Conference on Nuclear Engineering(ICONE 2016), Charlotte, North Carolina of USA, 2016-6-26 to 2016-6-30
18 王岩; 杨燕宁; 张尧力; 周志伟. 非能动安全壳冷却系统模拟分析程序PCCSAP-3D及其验证. 核动力工程, 2016, 37(2): 175-179
19 Wang yan; Zhang yao; Zhou zhiwei; Xie heng; Yang yanning. Study of the influence of design parameters and initial condition on passive containment cooling system. International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015, Hyatt Regency, Chicago, Illinois, USA, 2016-8-30 to 2016-9-4
20 王岩; 石磊; 郑艳华. 高温气冷堆蒸汽发生器卸压过程模拟和分析. 原子能科学技术, 2015, 49: 205-208
21 Wang yan; Li fu; Zheng yanhua. Discussion on Design Transients of Pebble-bed High Temperature Gas-cooled Reactor. 7th Innternational Topical Meeting on High Temperature Reaactor Technology(HTR2014), Weihai, Shandong Province, China, 2014-10-27 to 2014-10-31
22 Yan Wang. Preliminary Study for the Passive Containment Cooling System Analysis of the Advanced PWR. Energy Procedia, 2013, 39: 240-247
23 Wang yan; Yang yanning. Sensitivity study on the performance of the passive containment cooling system of the advanced pressurized water reactor. International Congress on Advances in Nuclear Power Plants, ICAPP 2013, Jeju Island, Korea, 2013-4-14 to 2013-4-18
24 Wang yan. Study on Pressure Relief Transient for High Temperature Gas Cooled Reactor. International Conference on Nuclear Engineering and the ASME 2012 Power Conference, ICONE 2012-POWER 2012, Anaheim, California, USA, 2012-7-30 to 2012-8-3
25 Wang yan. Analysis model for the passive containment cooling system. Journal of Convergence Information Technology, 2012, 7(3): 75-83
26 张尧立，杨燕宁，周志伟，王岩. PCCSAP-3D程序压力场算法改进. 计算物理, 2012, (29)5
27 Wangy yan. The Prospect of the Modeling Simulation for the Passive Containment Cooling System of the Advanced PWR in China. Applied Mechanics and Materials, 2011, 88: 82-87
28 葛枫; 王岩. 堆芯流量分配对反应堆热工影响的初步研究. 中国核科学技术进展报告（第五卷）——中国核学会2017年学术年会论文集第10册（核测试与分析分卷、核安全分卷）, 2017, 10: 335-340
29 王岩; 石磊; 李富; 郑艳华 模块式高温气冷堆换热管断裂事故进水量研究.中国核学会2011学术年会, 中国核科学技术进展报告 (第二卷)——中国核学会 2011 年学术年会论文集第 3 册 (核能动力分卷 (下)，贵阳市国际生态会议中心, 2011-10-11至2011-10-14
30 Wang yan; Han liyong. Study on the simulation for the passive containment cooling system of the advanced PWR in China. International Symposium on Future I&C for nuclear plant/Cognitive Systems Engineering in Process Control/International Symposium on Symbiotic Nuclear Power Systems(ICI2011), Daejeon Convention Center (DCC), Daejeon, Republic of Korea 2011-8-21至2011-8-25
