反应堆高温结构力学与完整性评估

082701-核能科学与工程

熔盐堆高温结构完整性评定技术研究

2015-09--2019-01   中国科学院大学   博士研究生
2009-09--2012-01   北京航空航天大学   硕士研究生
2005-09--2009-06   郑州大学   本科

   

2012-04~现在, 中国科学院上海应用物理研究所, 高级工程师

   

（1） 三八红旗手, , 研究所（学校）, 2021

   

[1] Wei Gong, Xiaoyan Wang, Chaochao Huang, Xiao Wang, Yuan Fu. Layout optimization for the high-temperature nuclear loop with movable equipment based on TMSR-LF1. ANNALS OF NUCLEAR ENERGY. 2024, 第 2 作者  通讯作者  199: http://dx.doi.org/10.1016/j.anucene.2024.110362.
[2] Rencong,Dai, Wei,Gong, Xiao,Wang, Xiaoyan,Wang, Decheng,Cui, Emanuele,Brunesi. Conservativeness Study on the Seismic Analysis Method for Research Reactor Plant Structure Based on TMSR-LF1. Advances in Civil Engineering. 2024, 第 4 作者2024: https://dx.doi.org/10.1155/2024/1672269.
[3] Xia, Chuxue, Cai, Maoyuan, Huang, Chaochao, Wang, Xiaoyan, Wang, Xiao. Computational method for added mass of single graphite brick in molten salt reactor. NUCLEAR ENGINEERING AND DESIGN[J]. 2023, 第 4 作者411: http://dx.doi.org/10.1016/j.nucengdes.2023.112418.
[4] Wang, XiaoYan, Gong, Wei, Wang, Xiao, Yu, Kun. Numerical investigation of creep crack growth behavior of UNS N10003 alloy based on the creep damage model. INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING[J]. 2022, 第 1 作者200: http://dx.doi.org/10.1016/j.ijpvp.2022.104838.
[5] Liu, Yicheng, Wang, Xiao, Wang, Xiaoyan, Zhang, Xiaochun, Gong, Wei, Dai, Rencong. Floor response spectra analysis of a nuclear reactor considering uncertainties in soil parameters. STRUCTURES[J]. 2022, 第 3 作者  通讯作者  37: 305-317, http://dx.doi.org/10.1016/j.istruc.2022.01.014.
[6] 刘艺诚, 王晓, 王晓艳, 樊辉青, 张小春. 土壤-结构相互作用下的TMSR-LF1厂房楼层反应谱分析. 核技术[J]. 2021, 第 3 作者44(7): 85-92, http://lib.cqvip.com/Qikan/Article/Detail?id=7105091338.
[7] 龚玮, 张小春, 王晓艳, 薛静怡, 傅远. 基于PepS的高温核一级管道蠕变疲劳分析方法研究. 核技术[J]. 2020, 第 3 作者43(3): 87-94, http://lib.cqvip.com/Qikan/Article/Detail?id=7101113609.
[8] Fan, HuiQing, Huang, ChaoChao, Wang, Xiao, Tsang, D K L, Zhang, XiaoChun, Wang, XiaoYan, Zhu, ShiFeng. Numerical simulation of stress behavior of dowel-brick structures in TMSR. NUCLEAR SCIENCE AND TECHNIQUES[J]. 2020, 第 6 作者31(5): 77-87, http://lib.cqvip.com/Qikan/Article/Detail?id=7101733771.
[9] Wang, XiaoYan, Wang, Xiao, Zhang, XiaoChun, Zhu, ShiFeng. Creep damage characterization of UNS N10003 alloy based on a numerical simulation using the Norton creep law and Kachanov-Rabotnov creep damage model. NUCLEAR SCIENCE AND TECHNIQUES[J]. 2019, 第 1 作者30(4): 65, http://lib.cqvip.com/Qikan/Article/Detail?id=7001719253.
[10] 王晓艳, 王晓, 张小春, 朱世峰. 基于损伤力学的TMSR-LF1堆容器接管非弹性蠕变损伤分析. 核技术[J]. 2019, 第 1 作者42(1): 60-65, http://lib.cqvip.com/Qikan/Article/Detail?id=7001139879.
[11] Fan, Huiqing, Huang, Chaochao, Zhang, Xiaochun, Wang, Xiaoyan, Zhu, Shifeng, Cai, Maoyuan, Wang, Xiao. Computational- and experimental-based analysis of the load capacity of dowel-brick structure of graphite component in TMSR. NUCLEAR ENGINEERING AND DESIGN[J]. 2019, 第 4 作者355: 
[12] Wang, XiaoYan, Zhu, ShiFeng, Wang, Xiao, Zhang, XiaoChun. Stress and thickness calculation of a bolted flat cover with double metal sealing rings. NUCLEAR SCIENCE AND TECHNIQUES[J]. 2018, 第 1 作者29(8): 120, http://lib.cqvip.com/Qikan/Article/Detail?id=675982276.
[13] Wang XY, Zhu SF, Wang X, Cao Y. STRESS ANALYSIS AND STRUCTURAL INTEGRITY EVALUATIONS OF PRESSURE VESSEL IN MOLTEN SALT REACTOR. PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, 2016, VOL 3[J]. 2017, http://gateway.webofknowledge.com/gateway/Gateway.cgi?GWVersion=2&SrcApp=PARTNER_APP&SrcAuth=LinksAMR&KeyUT=WOS:000398984700036&DestLinkType=FullRecord&DestApp=ALL_WOS&UsrCustomerID=3a85505900f77cc629623c3f2907beab.
[14] 苏飞, 王晓艳, 梁伟, 李伟佳. 非晶铁磁纤维应力阻抗效应的理论分析. 中国科学:物理学 力学 天文学[J]. 2013, 第 2 作者43(7): 874-880, http://ir.sinap.ac.cn/handle/331007/13466.

   

（ 1 ） 钍基熔盐堆核能系统-高温结构力学, 负责人, 中国科学院计划, 2011-01--2024-12
（ 2 ） 吸收体热工设计, 负责人, 其他, 2023-06--2024-12
（ 3 ） 十四五科技基础设施“小型模块化钍基熔盐堆系统”-高温结构力学, 负责人, 国家任务, 2022-06--2029-06