Design of reactor pressure vessel for Qinshan phase II NPP project

被引:0
|
作者
Zhong, Yuan-Zhang [1 ]
Wang, Zhen-Quan [1 ]
机构
[1] Nucl. Power Inst. of China, Chengdu 610041, China
来源
| 2003年 / Yuan Zi Neng Chuban She卷 / 24期
关键词
Design - Leakage (fluid) - Nuclear power plants - Pressure vessels - Stress analysis;
D O I
暂无
中图分类号
学科分类号
摘要
The design, manufacture, installation and test of the RPV should meet its safety demand. Common codes and standards shall be evaluated prior to application to ensure the safety function of the RPV. During the design, manufacture, installation and test, the probabilities for abnormal leakage, rapid grow of leaks and damage should be minimized. After the strength design in the preliminary design stage, primary stress has been analyzed and evaluated to extended design condition, which results satisfy the various stress specification in the RCC-M-B.
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