| Autor: |
Ju-Hee Kim, Jong Sung Kim, Nam-Su Huh, Chang-Young Oh, Heung-Bae Park, Sung-Ho Lee, Hong-Yeol Bae, Yun Jae Kim, Nam-Young Hur, Seung-Geon Lee, Ji Soo Kim |
| Rok vydání: |
2011 |
| Předmět: |
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| Zdroj: |
Transactions of the Korean Society of Mechanical Engineers A. 35:1337-1345 |
| ISSN: |
1226-4873 |
| DOI: |
10.3795/ksme-a.2011.35.10.1337 |
| Popis: |
In pressurized water reactors (PWRs), the reactor pressure vessel (RPV) upper head contains numerous control rod drive mechanism (CRDM) nozzles. In the last 10 years, the incidences of cracking in alloy 600 CRDM nozzles and their associated welds has increased significantly. Several axial and circumferential cracks have been found in CRDM nozzles in European PWRs and U.S. nuclear power plants. These cracks are caused by primary water stress corrosion cracking (PWSCC) and have been shown to be driven by welding residual stresses and operational stresses in the weld region. Therefore, detailed finite-element (FE) simulations for the Korea Nuclear Reactor Pressure Vessel have been conducted in order to predict the magnitudes of the weld residual stresses in the tube materials. In particular, the weld residual stress results are compared in terms for nozzle location, geometry factor/t, geometry of fillet, and adjacent nozzle. |
| Databáze: |
OpenAIRE |
| Externí odkaz: |
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