Effect of Normal Operating Condition Analysis Method for Weld Residual Stress of CRDM Nozzle in Reactor Pressure Vessel

被引:0
|
作者
Nam, Hyun Suk [1 ]
Bae, Hong Yeol [1 ]
Oh, Chang Young [1 ]
Kim, Ji Soo [1 ]
Kim, Yun Jae [1 ]
机构
[1] Korea Univ, Dept Mech Engn, Seoul, South Korea
关键词
Weld Residual Stress; Reactor Upper Vessel Head; Normal Operating Condition; FE Analysis; PWSCC;
D O I
10.3795/KSME-A.2013.37.9.1159
中图分类号
TH [机械、仪表工业];
学科分类号
0802 ;
摘要
In pressurized water nuclear reactors (PWRs), the reactor pressure vessel (RPV) upper head contains penetration nozzles that use a control rod drive mechanism (CRDM). The penetration nozzle uses J-groove weld geometry. Recently, the occurrence of cracking in alloy 600 CRDM penetration nozzle has increased. This is attributable to primary water stress corrosion cracking (PWSCC). PWSCC is known to be susceptible to the welding residual stress and operational stress. Generally, the tensile residual stress is the main factor contributing to crack growth. Therefore, this study investigates the effect on weld residual stress through different analysis methods for normal operating conditions using finite element analysis. In addition, this study also considers the effect of repeated normal operating condition cycles on the weld residual stress. Based on the analysis result, this paper presents a normal operating condition analysis method.
引用
收藏
页码:1159 / 1168
页数:10
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