Grade 91 강의 고온 균열진전 실험 결과와 설계 물성치의 비교

국문 초록 (Abstract)

본 연구에서는 피로 하중 및 크리프 하중을 받는 Mod.9Cr-1Mo (ASME Grade 91)강 시편에 대한 일련의 실험결과로부터 재료물성치인 고온 균열진전 모델을 개발하였다. 이 균열진전 모델은 크리프-피로하중을 받는 균열체의 결함평가에 사용되는 물성치이다. 한국원자력연구원이 수행한 일련의 피로 균열진전(FCG) 속도 실험 및 크리프 균열진전(CCG) 속도 실험 결과로부터 균열진전 모델을 결정하고, 이를 프랑스의 고온 설계 기술기준인 RCC-MRx 와 비교함으로써 설계 물성치의 보수성에 대해 검토하였다. RCC-MRx 는 FCG 모델 및 CCG 모델을 Section III Tome 6 에서 제공하고 있는데, 실험으로부터 결정한 균열진전 모델과 비교한 결과 RCC-MRx 의 FCG 모델은 보수적인 것으로 나타난 반면 CCG 모델은 비보수적인 것으로 나타나 동 물성치에 대한 검증이 필요한 것으로 나타났다. 또한 본 연구에서는 기계적 강도 및 크리프 시험결과에 대해서도 RCC-MRx 의 물성치와 비교 및 분석하였다.

다국어 초록 (Multilingual Abstract)

The material properties of crack growth models at an elevated temperature were derived from the results of numerous crack growth tests for Mod.9Cr-1Mo (ASME Grade 91) steel specimens under fatigue loading and creep loading at an elevated temperature. These crack growth models were needed for defect assessment under creep-fatigue loading. The mathematical crack growth rate models for fatigue crack growth (FCG) and creep crack growth (CCG) were determined based on the test results, and the models were compared with those of the French design code RCCMRx to investigate the conservatism of the code. The French design code RCC-MRx provides an FCG model and a CCG model for Grade 91 steel in Section III Tome 6. It was shown that the FCG model of RCC-MRx is conservative, while the CCG model is non-conservative compared with the present test data. Thus, it was shown that further validation of the property was required. Mechanical strength tests and creep tests were also conducted, and the test results were compared with those of RCC-MRx.

목차 (Table of Contents)

• 초록
• Abstract
• 1. 서론
• 2. 제 4 세대 원자로용 Gr.91 강
• 3. Gr.91 강의 고온 재료 시험
• 4. 결론
• 참고문헌(References)

참고문헌 (Reference)

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