核反应堆压力容器的热-机械耦合及断裂分析

doi:10.3969/j.issn.0253-2778.2017.06.007

中国科学技术大学学报 ›› 2017, Vol. 47 ›› Issue (6): 491-497.DOI: 10.3969/j.issn.0253-2778.2017.06.007

核反应堆压力容器的热-机械耦合及断裂分析

孙欣，柴国钟，鲍雨梅

浙江工业大学特种装备制造与先进加工技术教育部/浙江省重点实验室，浙江杭州 310014

收稿日期:2016-07-27 修回日期:2016-12-08 出版日期:2017-06-30 发布日期:2017-06-30
通讯作者: 柴国钟
作者简介:孙欣，男，1979年生，博士生.研究方向：断裂力学及其工程应用.E-mail: sunxin0912@163.com
基金资助:
国家自然科学基金(51275471, 51105339)资助.

Coupled thermo-mechanical and fracture analysis of a nuclear reactor pressure vessel

SUN Xin, CHAI Guozhong, BAO Yumei

Key Laboratory of Special Purpose Equipment and Advanced Manufacturing Technology, Ministry of Education & Zhejiang Province, Zhejiang University of Technology, Hangzhou 310014, China

Received:2016-07-27 Revised:2016-12-08 Online:2017-06-30 Published:2017-06-30

摘要/Abstract

摘要： 为研究承压热冲击对含表面裂纹的核反应堆压力容器（reactor pressure vessel, RPV）的承载能力的影响，利用ABAQUS软件对裂纹周围的环带区建立三维有限元模型，得到了瞬态温度场和应力场.使用扩展有限元法对热-机械耦合场中裂纹的扩展情况进行模拟.对不同的无延性转变温度下容器的极限承载力进行了弹塑性断裂分析，并与弹性分析的结果进行对比，总结出材料的断裂特性.通过网格的细化发现，由不同单元尺寸得到的裂纹扩展路径及损伤程度是相当的，从而避免了病态网格的依赖性.

关键词: 反应堆压力容器, 承压热冲击, 扩展有限元法, 无延性转变温度

Abstract: To study the influence of pressurized thermal shock on the bearing capacity of the nuclear reactor pressure vessel (RPV) with a surface crack, the 3D finite element model was established for the beltline region around the crack by ABAQUS software. The transient temperature field and stress field were obtained. The XFEM was used to simulate the crack propagation in the thermo-mechanical coupling field. The ultimate bearing capacity of the vessel at different nil-ductility transition temperatures was tested employing elastic-plastic fracture analysis, and the results were compared with those obtained from elastic analysis to sum up the fracture characteristics of the material. Through mesh refinement, it was found that the crack propagation paths and the damage degrees for different element sizes are equivalent, which avoids pathological mesh dependence.

Key words: reactor pressure vessel, pressurized thermal shock, XFEM, nil-ductility transition temperature

中图分类号:

O346.1
TL341

孙欣，柴国钟，鲍雨梅. 核反应堆压力容器的热-机械耦合及断裂分析[J]. 中国科学技术大学学报, 2017, 47(6): 491-497.

SUN Xin, CHAI Guozhong, BAO Yumei. Coupled thermo-mechanical and fracture analysis of a nuclear reactor pressure vessel[J]. Journal of University of Science and Technology of China, 2017, 47(6): 491-497.

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核反应堆压力容器的热-机械耦合及断裂分析

Coupled thermo-mechanical and fracture analysis of a nuclear reactor pressure vessel

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