原子能科学技术 ›› 2014, Vol. 48 ›› Issue (11): 2078-2084.DOI: 10.7538/yzk.2014.48.11.2078

• 反应堆工程 • 上一篇    下一篇

承压热冲击下压力容器断裂力学分析

许雷雷;梁国兴   

  1. 上海交通大学 核科学与工程学院，上海200240
  • 出版日期:2014-11-20 发布日期:2014-11-20

Fracture Mechanics Analysis for Reactor Pressure Vessel Under Pressurized Thermal Shock

XU Lei-lei;LIANG Guo-xing   

  1. School of Nuclear Science and Engineering, Shanghai Jiao Tong University,Shanghai 200240, China
  • Online:2014-11-20 Published:2014-11-20

PDF

摘要：

依据美国核管会（NRC）最新法规要求和研究进展，阐述了压水堆核电厂反应堆压力容器（RPV）承压热冲击（PTS）最新评估方法。基于热工水力系统程序RELAP5和有限元分析软件ANSYS，针对某传统二代压水堆核电厂模拟在PTS典型瞬态过程下热工响应行为及压力容器模型断裂力学分析，并评估不同瞬态的危险性及其随压力容器材料脆性的变化。分析表明：表面裂纹和靠近内壁面的埋藏裂纹比深埋裂纹更易发生开裂；同等条件下轴向裂纹较环向裂纹更易开裂，且大中破口事故下轴向裂纹远较环向裂纹更易贯穿壁厚。

关键词: 反应堆压力容器, 承压热冲击, 断裂力学

Abstract:

Based on the requirements of latest codes and rules and the research achievements of US NRC, the analysis methodology for reactor pressure vessel (RPV) structure integrity under pressurized thermal shock (PTS) was presented. For a series of PTS transients, the thermal-hydraulic responses of a typical conventional PWR were calculated with the thermal-hydraulic system analysis program RELAP5, and fracture mechanics analyses of the RPV model were calculated with the finite element analysis software ANSYS. Furthermore, the risk assessment was performed under these PTS transients, and the effect of RPV material embrittlement was studied. The analyses indicate that the surface flaws and the flaws close to the interior surface of the RPV are more vulnerable to produce crack initiation than those deeper in the RPV wall. Besides, axial flaws are more vulnerable to produce crack initiation than circumferential flaws under the same conditions, and axial flaws are much more likely than circumferential flaws to propagate through the RPV wall in medium and large diameter breaks.

Key words: reactor pressure vessel, pressurized thermal shock, fracture mechanics