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자료유형
학술저널
저자정보
저널정보
한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제48권 제6호
발행연도
2016.1
수록면
1,412 - 1,422 (11page)

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Austenitic stainless steels (ASSs) are widely used for nuclear pipes as they exhibit a goodcombination of mechanical properties and corrosion resistance. However, high tensileresidual stresses may occur in ASS welds because postweld heat treatment is not generallyconducted in order to avoid sensitization, which causes a stress corrosion crack. In thisstudy, round robin analyses on stress intensity factors (SIFs) were carried out to examinethe appropriateness of structural integrity assessment methods for ASS pipe welds withtwo types of circumferential cracks. Typical stress profiles were generated from finiteelement analyses by considering residual stresses and normal operating conditions. Then,SIFs of cracked ASS pipes were determined by analytical equations represented in fitnessfor-service assessment codes as well as reference finite element analyses. The discrepanciesof estimated SIFs among round robin participants were confirmed due to differentassessment procedures and relevant considerations, as well as the mistakes of participants. The effects of uncertainty factors on SIFs were deducted from sensitivity analysesand, based on the similarity and conservatism compared with detailed finite elementanalysis results, the R6 code, taking into account the applied internal pressure and combinationof stress components, was recommended as the optimum procedure for SIFestimation.

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