TY - JOUR
T1 - Effect of normal operating condition analysis method for weld residual stress of CRDM nozzle in reactor pressure vessel
AU - Nam, Hyun Suk
AU - Bae, Hong Yeol
AU - Oh, Chang Young
AU - Kim, Ji Soo
AU - Kim, Yun Jae
PY - 2013/9
Y1 - 2013/9
N2 - 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.
AB - 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.
KW - FE analysis
KW - Normal operating condition
KW - PWSCC
KW - Reactor upper vessel head
KW - Weld residual stress
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U2 - 10.3795/KSME-A.2013.37.9.1159
DO - 10.3795/KSME-A.2013.37.9.1159
M3 - Article
AN - SCOPUS:84898434925
SN - 1226-4873
VL - 37
SP - 1159
EP - 1168
JO - Transactions of the Korean Society of Mechanical Engineers, A
JF - Transactions of the Korean Society of Mechanical Engineers, A
IS - 9
ER -