原子能科学技术 ›› 2017, Vol. 51 ›› Issue (8): 1407-1412.DOI: 10.7538/yzk.2017.51.08.1407

• 反应堆工程 • 上一篇    下一篇

LOCA下具有表面裂纹的反应堆压力容器承压热冲击分析

陆维;何铮   

  1. 国家核电技术有限公司 北京研发中心,北京100190
  • 出版日期:2017-08-20 发布日期:2017-08-20

PTS Analysis of RPV Structure with Surface Crack under LOCA

LU Wei;HE Zheng   

  1. State Nuclear Power Technology R&D Center (Beijing), Beijing 100190, China
  • Online:2017-08-20 Published:2017-08-20

摘要:

失水事故(LOCA)瞬态下,具有半椭圆形表面裂纹的反应堆压力容器(RPV)承压热冲击(PTS)问题被研究。采用有限元方法计算瞬态过程的热-应力响应;采用影响函数法计算应力强度因子,分别对母材和堆焊层内的应力进行分解,从而解决了由于堆焊层存在造成的应力拟合困难带来的计算偏差。编制了相应的断裂分析程序,对LOCA下RPV的结构完整性进行了分析。结果表明,在研究的LOCA下,整个瞬态过程中RPV应力强度因子均未超过材料断裂韧性,压力容器结构安全。本文研究为RPV在PTS下的结构完整性评估提供理论指导。

关键词: 承压热冲击, 表面裂纹, 影响函数法, 应力强度因子

Abstract:

The pressurized thermal shock (PTS) analysis of a reactor pressure vessel (RPV) with a semi-elliptical surface crack was performed under loss of coolant accident (LOCA) transient. The finite element method (FEM) was adopted to calculate the thermal-stress responses. Stress-intensity factor (SIF) was calculated by influence function method. Stress distributions in the base material and bead welding layer were decomposed, so that the difficulty of stress fitting caused by existence of bead welding layer was conquered. A fracture analysis program was developed in present research to analyze the RPV integrity under LOCA. The results show that during the whole LOCA transient, SIF of RPV crack does not exceed fracture toughness, which means RPV structure is safe. The present research will provide a theoretical guidance for RPV integrity assessment under PTS.

Key words: pressurized thermal shock, surface crack, influence function method, stress-intensity factor