Abstract
In nuclear power plants, the reactor pressure vessel (RPV) upper head control rod drive mechanism (CRDM) penetration nozzles are fabricated using J-groove weld geometry. Recently, the incidences of cracking in Alloy 600 CRDM nozzles and their associated welds have increased significantly. The cracking mechanism has been attributed to primary water stress corrosion cracking (PWSCC), and it has been shown to be driven by welding residual stresses and operational stresses in the weld region. The weld-induced residual stress is the main factor contributing to crack growth. Therefore, an exact estimation of the residual stress is important for ensuring reliable operation. This study presents the residual stress computation performed for an RPV CRDM penetration nozzle in Korea. Based on two and three dimensional finite element analyses, the effect of welding variables on the residual stress variation is estimated for sensitivity analysis.
Original language | English |
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Pages (from-to) | 1115-1130 |
Number of pages | 16 |
Journal | Transactions of the Korean Society of Mechanical Engineers, A |
Volume | 36 |
Issue number | 10 |
DOIs | |
Publication status | Published - 2012 Oct |
Externally published | Yes |
Keywords
- BMI
- CRDM
- FEA
- J-groove weld
- PWSCC
- RPV
- Sensitivity Analysis
ASJC Scopus subject areas
- Mechanical Engineering