首页 | 本学科首页   官方微博 | 高级检索  
     

反应堆压力容器在典型过冷瞬态下的断裂力学分析
引用本文:张万平,曹明,黄庆,贺寅彪. 反应堆压力容器在典型过冷瞬态下的断裂力学分析[J]. 计算机辅助工程, 2006, 15(Z1): 264-267
作者姓名:张万平  曹明  黄庆  贺寅彪
作者单位:上海核工程研究设计院,上海,200233
摘    要:考虑反应堆压力容器在役期间可能发生的典型的过冷瞬态(大破口失水和小破口失水事故),针对不同的裂纹形式运用MSC Marc程序进行断裂力学分析,进而确定容器在哪种裂纹和哪种瞬态下最危险,分析中考虑了堆焊层对断裂分析的影响. 运用有限元法进行断裂力学分析结果与理论解进行比较,二者吻合较好.

关 键 词:反应堆压力容器(RPV)  过冷瞬态  断裂力学
文章编号:1006-0871(2006)S1-0264-04
修稿时间:2006-07-14

Fracture Mechanics Analysis for Reactor Pressure Vessel under Overcooling Transient
ZHANG Wanping,CAO Ming,HUANG Qing,HE Yinbiao. Fracture Mechanics Analysis for Reactor Pressure Vessel under Overcooling Transient[J]. Computer Aided Engineering, 2006, 15(Z1): 264-267
Authors:ZHANG Wanping  CAO Ming  HUANG Qing  HE Yinbiao
Abstract:The fracture mechanics analysis for different flaw is illustrated using MSC Marc. During the typical overcooling transients (LBLOCA and SBLOCA) for RPV in service, comparison is made to probe what kind of flaw and what kind of transient are most dangerous. The influence of the cladding on the fracture analysis is investigated. The fracture analysis results between finite element method and theoretic method have a good agreement.
Keywords:MSC Marc
本文献已被 CNKI 万方数据 等数据库收录!
设为首页 | 免责声明 | 关于勤云 | 加入收藏

Copyright©北京勤云科技发展有限公司  京ICP备09084417号