메뉴 건너뛰기
.. 내서재 .. 알림
소속 기관/학교 인증
인증하면 논문, 학술자료 등을  무료로 열람할 수 있어요.
한국대학교, 누리자동차, 시립도서관 등 나의 기관을 확인해보세요
(국내 대학 90% 이상 구독 중)
로그인 회원가입 고객센터 ENG
주제분류

추천
검색

논문 기본 정보

자료유형
학술저널
저자정보
저널정보
한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제47권 제7호
발행연도
2015.1
수록면
895 - 906 (12page)

이용수

표지
📌
연구주제
📖
연구배경
🔬
연구방법
🏆
연구결과
AI에게 요청하기
추천
검색

초록· 키워드

오류제보하기
Background: Mitigation of primary water stress corrosion cracking (PWSCC) is a significantissue in the nuclear industry. Advanced nickel-based alloys with lower susceptibility havebeen adopted, although they do not seem to be entirely immune from PWSCC duringnormal operation. With regard to structural integrity assessments of the relevant components,an accurate evaluation of crack growth rate (CGR) is important. Methods: For the present study, the extended finite element method was adopted fromamong diverse meshless methods because of its advantages in arbitrary crack analysis. Auser-subroutine based on the strain rate damage model was developed and incorporatedinto the crack growth evaluation. Results: The proposed method was verified by using the well-known Alloy 600 material witha reference CGR curve. The analyzed CGR curve of the alternative Alloy 690 material wasthen newly estimated by applying the proven method over a practical range of stress intensityfactors. Conclusion: Reliable CGR curves were obtained without complex environmental facilities ora high degree of experimental effort. The proposed method may be used to assess thePWSCC resistance of nuclear components subjected to high residual stresses such as thoseresulting from dissimilar metal welding parts.

목차

등록된 정보가 없습니다.

참고문헌 (18)

참고문헌 신청

함께 읽어보면 좋을 논문

논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!

이 논문의 저자 정보

최근 본 자료

전체보기

댓글(0)

0