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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2020.1
- 수록면
- 1,051 - 1,065 (15page)
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초록· 키워드
오류제보하기
Safety analysis of nuclear power plant (NPP) especially in accident conditions is a basic and necessaryissue for applications and commercialization of reactors. Many previous researches and developmentworks have been conducted. However, most achievements focused on the safety reliability of primarypressure system vessels. Few literatures studied the structural safety of huge concrete structures surroundingprimary pressure system, especially for the fourth generation NPP which allows existing ofthrough cracks. In this paper, structural safety reliability of concrete structures of HTR-PM in accidentaldouble-ended break of hot gas ducts was studied by Exceedance Probability Method. It was calculatedby Monte Carlo approaches applying numerical simulations by Abaqus. Damage parameters wereproposed and used to define the property of concrete, which can perfectly describe the crack state ofconcrete structures. Calculation results indicated that functional failure determined by deterministicsafety analysis was decided by the crack resistance capability of containment buildings, whereas thebearing capacity of concrete structures possess a high safety margin. The failure probability of concretestructures during an accident of double-ended break of hot gas ducts will be 31.18%. Adding theconsideration the contingency occurrence probability of the accident, probability of functional failure issufficiently low.
목차
등록된 정보가 없습니다.
참고문헌 (26)
참고문헌 신청
Z. Wu / 2002 / The design features of the HTR-10 / Nucl. Eng. Des 218:25~32
Z. Zhang / 2009 / Current status and technical description of Chinese 2·250 MW th HTR-PM demonstration plant / Nucl. Eng. Des 239:1212~1219
C. Fang / 2016 / The R&D of HTGR high temperature helium sampling loop : from HTR-10 to HTR-PM / Nucl. Eng. Des 306:192~197
A. Dvorzhak / 2016 / Probabilistic risk assessment from potential exposures to the public applied for innovative nuclear installations / Reliab. Eng. Syst. Saf 152:176~186
R. Barati / 2013 / Functional reliability evaluation of an MTR-pool type research reactor core using the loadecapacity interference model / Ann. Nucl. Energy 58:151~160
Z. Zhang / 2009 / Current status and technical description of Chinese 2·250 MW th HTR-PM demonstration plant / Nucl. Eng. Des 239:1212~1219
C. Fang / 2016 / The R&D of HTGR high temperature helium sampling loop : from HTR-10 to HTR-PM / Nucl. Eng. Des 306:192~197
A. Dvorzhak / 2016 / Probabilistic risk assessment from potential exposures to the public applied for innovative nuclear installations / Reliab. Eng. Syst. Saf 152:176~186
R. Barati / 2013 / Functional reliability evaluation of an MTR-pool type research reactor core using the loadecapacity interference model / Ann. Nucl. Energy 58:151~160
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