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서지반출
가동중 중수로 압력관의 외경과 두꼐 변화를 고려한 결함의 파손확률 예측
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  • 가동중 중수로 압력관의 외경과 두꼐 변화를 고려한 결함의 파손확률 예측
저자명
곽상록,이준성,김영진,박윤원,Kwak. Sang-Log,Lee. Joon-Seong,Kim. Young-Jin,Park. Youn-Won
간행물명
大韓機械學會論文集. Transactions of the Korean Society of mechanical engineers. A. A
권/호정보
2002년|26권 11호|pp.2305-2311 (7 pages)
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대한기계학회
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정기간행물|
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이 논문은 한국과학기술정보연구원과 논문 연계를 통해 무료로 제공되는 원문입니다.
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기타언어초록

The pressure tube is a major component of the CANDU reactor, which supports nuclear fuel bundle and heavy water coolant. Pressure tubes are installed horizontally inside the reactor and only selected samples are periodically examined during in-service inspection. In this respect, a probabilistic safety assessment method is more appropriate fur the assessment of overall pressure tube safety. The failure behavior of CANDU pressure tubes, however, is governed by delayed hydride cracking which is the major difference from pipings and reactor pressure vessels. Since the delayed hydride cracking has more widely distributed governing parameters, it is impossible to apply a general PFM methodology directly. In this paper, a PFM methodology for the safety assessment of CANDU pressure tubes is introduced by applying Monte Carlo simulation in determining failure probability Initial hydrogen concentration, flaw shape and depth, axial and radial crack growth rate and fracture toughness were considered as probabilistic variables. Parametric study has been done under the base of pressure tube dimension and hydride precipitation temperature in calculating failure probability. Unstable fracture and plastic collapse are used for the failure assessment. The estimated failure probability showed about three-order difference with changing dimensions of pressure tube.