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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2013.6
- 수록면
- 518 - 524 (7page)
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초록· 키워드
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Recently, probabilistic assessments of nuclear power plant components have generated interest in the nuclear industries, either for the efficient inspection and maintenance of older nuclear plants or for improving the safety and cost-effective design of newly constructed nuclear plants. In the present paper, the partial safety factor (PSF) of wall-thinned nuclear piping is evaluated based on a reliability index method, from which the effect of each statistical variable (assessment parameter) on a certain target probability is evaluated. In order to calculate the PSF of a wall-thinned pipe, a limit state function based on the load and resistance factor design (LRFD) concept is first constructed. As for the reliability assessment method, both the advanced first-order second moment (AFOSM) method and second-order reliability method (SORM) are employed to determine the PSF of each probabilistic variable. The present results can be used for developing maintenance strategies considering the priorities of input variables for structural integrity assessments of wall-thinned piping, and this PSF concept can also be applied to the optimal design of the components of newly constructed plants considering the target reliability levels.
목차
ABSTRACT
1. 서론
2. 부분안전계수 평가 이론
3. 감육배관의 PSF 계산을 위한 한계상태함수
4. 부분안전계수 계산 프로그램
5. 감육배관의 부분안전계수 계산
6. 결론
References
참고문헌 (9)
참고문헌 신청
1. [학술지(정기간행물)] - DOHEE HAHN / 2007 / CONCEPTUAL DESIGN OF THE SODIUM-COOLED FAST REACTOR KALIMER-600 / Nuclear Engineering and Technology 39 (3) : 193 ~ 206
2. [학술대회논문] - Lee, J. H. / 2007 / Structural Concept Design of KALIMER-600 Sodium Cooled Fast Reactor / Proceedings of KSME Spring Annual Conference : 37 ~ 42
3. [학술대회논문] - Bloom, J. M. / 2000 / Partial Safety Factors(PSF)and Their Impact on ASME Section XI, IWB-3610 / ASME Pressure Vessels and Piping Conference PVP : 407 ~
4. [단행본] - Thoft-Christensen, P. / 1982 / Structural Reliability Theory and Its Applications / Springer-Verlag Berlin : 81 ~ 93
5. [학술대회논문] - Leis, B. N. / 1997 / An Alternative Approach to Assess the Integrity of Corroded Line Pipe part I: Current Status, part II: Alternative Criterion / Proceeding of 7th International Offshore and Polar Engineering Conference : 624 ~ 641
2. [학술대회논문] - Lee, J. H. / 2007 / Structural Concept Design of KALIMER-600 Sodium Cooled Fast Reactor / Proceedings of KSME Spring Annual Conference : 37 ~ 42
3. [학술대회논문] - Bloom, J. M. / 2000 / Partial Safety Factors(PSF)and Their Impact on ASME Section XI, IWB-3610 / ASME Pressure Vessels and Piping Conference PVP : 407 ~
4. [단행본] - Thoft-Christensen, P. / 1982 / Structural Reliability Theory and Its Applications / Springer-Verlag Berlin : 81 ~ 93
5. [학술대회논문] - Leis, B. N. / 1997 / An Alternative Approach to Assess the Integrity of Corroded Line Pipe part I: Current Status, part II: Alternative Criterion / Proceeding of 7th International Offshore and Polar Engineering Conference : 624 ~ 641
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