基本信息
张小春 女 硕导 中国科学院上海应用物理研究所
电子邮件: zhangxiaochun@sinap.ac.cn
通信地址: 上海市嘉定区嘉罗公路2019号
邮政编码: 201800
电子邮件: zhangxiaochun@sinap.ac.cn
通信地址: 上海市嘉定区嘉罗公路2019号
邮政编码: 201800
招生信息
招生专业
082701-核能科学与工程082703-核技术及应用
招生方向
高温结构完整性分析与安全评估技术;堆用设备抗震设计与分析技术
教育背景
2008-08--2012-10 The Hong Kong Polytechnic University Ph.D2005-09--2007-06 华中科技大学 硕士2001-09--2005-06 华中科技大学 本科
工作经历
工作简历
2021-01~2022-08,中国科学院上海应用物理研究所, 正研级高级工程师、副主任2017-01~2020-12,上海应用物理研究所, 高级工程师2014-01~2016-12,上海应用物理研究所, 助理研究员2012-10~2014-01,City University of Hong Kong, Senior Research Associate2011-03~2011-05,AREVA NP (Nuclear Plants) & National School of Engineering of Saint-Etienne (ENISE), Intern & Visiting Scholar2007-07~2008-07,City University of Hong Kong, Research Assistant
社会兼职
2021-11-29-2022-08-20,嘉定区人大代表,
2016-08-30-2022-07-31,中国核学会核工程力学分会理事会, 理事
2016-08-30-2022-07-31,中国核学会核工程力学分会理事会, 理事
专利与奖励
奖励信息
(1) 三八红旗手, 研究所(学校), 2021(2) 青年科技之星, 研究所(学校), 2020
出版信息
发表论文
(1) Floor response spectra analysis of a nuclear reactor considering uncertainties in soil parameters, STRUCTURES, 2022, 第 4 作者(2) A constitutive model incorporating grain refinement strengthening on metallic alloys, JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY, 2021, 通讯作者(3) 土壤-结构相互作用下的TMSR-LF1厂房楼层反应谱分析, 核技术, 2021, 第 4 作者(4) 镍基合金管道环形焊接与焊后热处理模拟, 热加工工艺, 2021, 第 2 作者(5) Numerical simulation of stress behavior of dowel–brick structures in TMSR, Numerical simulation of stress behavior of dowel-brick structures in TMSR, NUCLEAR SCIENCE AND TECHNIQUES, 2020, 通讯作者(6) 基于PepS的高温核一级管道蠕变疲劳分析方法研究, Application of PepS in creep-fatigue damage evaluation for class 1 nuclear piping at elevated temperature, 核技术, 2020, 通讯作者(7) Numerical and experimental comparison of two nano-structuring processing techniques on making stronger stainless steels, MATERIALS TODAY COMMUNICATIONS, 2020, 通讯作者(8) Structural Evaluation With Elastic and Inelastic Analysis Methods on a High Temperature Storage Tank Subjected to Static and Dynamic Loadings, Proceedings of the Asme Pressure Vessels and Piping Conference, 2020, 第 2 作者(9) Creep damage characterization of UNS N10003 alloy based on a numerical simulation using the Norton creep law and Kachanov-Rabotnov creep damage model, Creep damage characterization of UNS N10003 alloy based on a numerical simulation using the Norton creep law and Kachanov–Rabotnov creep damage model, 核技术:英文版, 2019, 通讯作者(10) 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, 2019, 通讯作者(11) TMSR-LF1停堆系统高温螺栓连接结构应力松弛分析与结构安全评定, Analysis and evaluation of stress relaxation for the high temperature bolt connecting structure in scram system of the TMSR-LF1, 核技术, 2019, 通讯作者(12) Predicting surface deformation during mechanical attrition of metallic alloys, NPJ COMPUTATIONAL MATERIALS, 2019, 通讯作者(13) 基于ANSYS的高温熔盐泵应力分析与结构优化, Stress analysis and structural analysis and optimization of high temperature molten salt pump in TMSR-SF0 based on ANSYS, 核技术, 2019, 通讯作者(14) 镍基合金压力容器环形焊缝残余应力数值模拟与失效应力分析, Numerical simulation of residual stress in girth weld and failure stress analysis of reactor vessel, 核技术, 2019, 通讯作者(15) 基于损伤力学的TMSR-LF1堆容器接管非弹性蠕变损伤分析, Inelastic creep damage analysis of RPV nozzle in TMSR-LF1 based on damage mechanics, 核技术, 2019, 第 3 作者(16) 核安全一级高温管道系统结构分析与安全评估方法研究, Structural Analysis and Evaluation Method for Nuclear Class 1 Piping Systems at Elevated Temperature, 核动力工程, 2019, 第 1 作者(17) Computational- and experimental-based analysis of the load capacity of dowel-brick structure of graphite component in TMSR, NUCLEAR ENGINEERING AND DESIGN, 2019, 第 3 作者(18) Stress and thickness calculation of a bolted flat cover with double metal sealing rings, NUCLEAR SCIENCE AND TECHNIQUES, 2018, 第 4 作者(19) Numerical Study on the Creep Strain Characteristics for Tmsr Reactor Coolant Piping under Thermal Loading, Proceedings of the Asme Pressure Vessels and Piping Conference, 2018, 第 2 作者
科研活动
科研项目
( 1 ) II类研究堆构筑物与设备分级及其抗震设计基准研究, 负责人, 地方任务, 2019-06--2020-11( 2 ) 未来先进核裂变能-钍基熔盐核能系统, 参与, 国家任务, 2014-01--2021-12
参与会议
(1)TMSR-LF1钍基熔盐堆高温主设备力学分析关键问题与解决方案 中国核学会核工程力学分会第二届学术交流 2020-10-23(2)核级高温复杂管系结构分析与安全评估方法研究 中国核学会核工程力学分会2018年学术交流会 2018-09-16(3)LF1 of TMSR at SINAP: Progress in structural analysis and design evaluation technology ASME Boiler and Pressure Vessel Committee Code Week 2018-05-06(4)反应堆堆本体结构系统抗震性能研究 第十九届全国反应堆结构力学会议 2016-10-18(5)Analytical Solutions and Structural Evaluation Method for TMSR Piping Components at Elevated Temperature ASME Boiler and Pressure Vessel Committee Code Week 2015-11-01(6)Stress Analysis and Optimum Design of the Heat Transport System at Molten Salt Reactor Asme Pressure Vessels and Piping Conference 2015-07-15