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논문 기본 정보

자료유형
학술저널
저자정보
David A. Collins (Oak Ridge National Laboratory) Emily L. Carter (Earth Systems Science Division, Pacific Northwest National Laboratory) Timothy G. Lach (Oak Ridge National Laboratory) Thak Sang Byun (Oak Ridge National Laboratory)
저널정보
한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제54권 제2호
발행연도
2022.2
수록면
709 - 731 (23page)

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초록· 키워드

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Loss of fracture resistance due to thermal aging degradation is a potential limiting factor affecting thelong-term (80þ year) viability of nuclear reactors. To evaluate the effects of decades of aging in apractical time frame, accelerated aging must be employed prior to mechanical characterization. In thisstudy, a variety of chemically and microstructurally diverse austenitic stainless steels were aged between0 and 30,000 h at 290e400 C to simulate 0e80þ years of operation. Over 600 static fracture tests werecarried out between room temperature and 400 C. The results presented include selected J-R curves ofeach material as well as K0.2mm fracture toughness values mapped against aging condition and ferritecontent in order to display any trends related to those variables. Results regarding differences in processing, optimal ferrite content under light aging, and the relationship between test temperature and Mocontent were observed. Overall, it was found that both the ferrite volume fraction and molybdenumcontent had significant effects on thermal degradation susceptibility. It was determined that materialswith >25 vol% ferrite are unlikely to be viable for 80 years, particularly if they have high Mo contents(>2 wt%), while materials less than 15 vol% ferrite are viable regardless of Mo content.

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