• 한국압력기기공학회 논문집
• /
• 제11권2호
• /
• pp.25-30
• /
• 2015

In the present study, complex leakage probabilities of nuclear pipes due to fatigue and stress corrosion cracking are evaluated by using the PINTIN(Piping INTegrity INner flaws) that is developed based on the existing PRAISE(Piping Reliability Analysis Including Seismic Events) program. With regard to the aging and crack instability, small leak and big leak probabilities are calculated for several pipes in a reactor coolant system of domestic nuclear plant. Moreover, sensitivity analysis is also performed to find out the effect of parameters for the leakage of pipes, which shows the coolant temperature is the most influencing parameter.

• 한국안전학회지
• /
• 제12권2호
• /
• pp.3-16
• /
• 1997

In modern high performance engineering applications, the structural integrity of materials and structures are quite often evaluated using fracture mechanics. This evaluation in turn requires information on the flaw geometry (location, type, shape, size, and orientation). The ultrasonic nondestructive evaluation (NDE) method is one technique that is commonly used to provide such information. Flaw classification (determination of the flaw type ) and flaw sizing (prediction of the flaw shape, orientation and sizing parameters) are very important issues for quantitative ultrasonic NDE. In this paper new approaches to both classification and sizing of flaws are described together with extensive review of previous works on both topics. In the area of flaw classification, a methodology is developed which can solve classification problems using probabilistic neural networks, and in the area of flaw sizing, a time-of-flight equivalent (TOFE) sizing method is presented. The techniques proposed here are in a form that can be used directly in many practical applications to quantitative estimates of the flaw's significance.

• 대한조선학회논문집
• /
• 제57권1호
• /
• pp.1-7
• /
• 2020

In general, an inspection schedule is established based on the long-term fatigue life during the design stage. However, in the design stage, it is difficult to clearly identify the uncertainty factors affecting long-term fatigue life. In this study, the probabilistic fatigue life assessment was conducted in accordance with the methodology of DNV-GL. Firstly, The initial crack distribution estimated through the initial crack propagation analysis was updated by reflecting the results of crack inspection. Secondly, the updated crack distribution was compared with the initial crack distribution, and the probability of failure was updated with the effect of crack inspection.

• Nuclear Engineering and Technology
• /
• 제48권6호
• /
• pp.1423-1432
• /
• 2016

The integrity of a reactor pressure vessel (RPV) related to pressurized thermal shocks (PTSs) has been extensively studied. This paper introduces an integrity assessment of an RPV subjected to a PTS transient based on the French codes. In the USA, the "screening criterion" for maximum allowable embrittlement of RPV material is developed based on the probabilistic fracture mechanics. However, in the French RCC-M and RSE-M codes, which are developed based on the deterministic fracture mechanics, there is no "screening criterion". In this paper, the methodology in the RCC-M and RSE-M codes, which are used for PTS analysis, are firstly discussed. The bases of the French codes are compared with ASME and FAVOR codes. A case study is also presented. The results show that the method in the RCC-M code that accounts for the influence of cladding on the stress intensity factor (SIF) may be nonconservative. The SIF almost doubles if the weld residual stress is considered. The approaches included in the codes differ in many aspects, which may result in significant differences in the assessment results. Therefore, homogenization of the codes in the long time operation of nuclear power plants is needed.

• Nuclear Engineering and Technology
• /
• 제52권1호
• /
• pp.185-191
• /
• 2020

Plant-specific analyses of an advanced reactor have been performed to assure the structural integrity of the reactor pressure vessel during transient conditions, which are expected to initiate pressurized thermal shock (PTS) events. The vessel failure probabilities from the probabilistic fracture mechanics analyses are combined with the transient frequencies to generate the through-wall cracking frequencies, which are compared to the acceptance criterion. Several sensitivity analyses are performed, focusing on the orientations and sizes of cracks, the copper content, and a flaw distribution model. The results show that the integrity of the reactor vessel is expected to be maintained for long-term operation beyond the design lifetime from the PTS perspective using the design data of the advanced reactor. Moreover, a fluence level exceeding 9×10¹⁹ n/㎠ is found to be acceptable, generating a sufficient margin beyond the design lifetime.

• 한국지반공학회논문집
• /
• 제20권4호
• /
• pp.89-102
• /
• 2004

디커플링장전조건의 화약 폭발시 발생하는 발파압력은 최대압력, 최대압력 도달시간, 압력파형의 함수로 나타난다. 발파 최대압력과 최대압력 도달시간은 화약과 암반 특성의 함수이다. 화약과 암반특성시험 결과로부터 그 특성치의 확률분포를 산출하였다. 화약과 암반 특성치의 확률분포가 정규분포로 나타났으므로 발파 최대압력과 최대압력 도달시간의 확률분포도 정규분포로 추정되었다. 발파 최대압력과 최대압력 도달시간에 가장 크게 영향을 미치는 변수를 파악하기 위하여 매개변수분석과 불확정성분석을 실행하였다. 최대압력과 최대압력 도달시간은 매개변수분석결과 화약특성에 가장 크게 영향을 받았지만 불확정성분석결과 화약보다 암반특성에 크게 영향을 받았다. 발파로 인하여 굴착선주 변 암반에 발생하는 손상을 수치해석으로 분석하였다. 암반손상을 산정하기 위하여 연속체손상역학에 기초하여 사용자 부 프로그램을 작성하였다. 이 부 프로그램을 ABAQUS 주 프로그램과 연결하여 해석하였다. 동적 해석결과는 확대공 발파에 의한 손상이 외곽공보다 크게 나타났다. 확대공 배치, 암반분류 세분화 등 여굴방지 방안이 제안되었다 손상계수의 파쇄기준이 불명확하므로 fuzzy-random 확률이론을 적용하여 파쇄기준과 파쇄영역을 명확하게 나타내었다.

• 비파괴검사학회지
• /
• 제18권5호
• /
• pp.389-397
• /
• 1998

Windows 95 환경하에서 PSI/ISI 데이터의 효율적 관리를 위한 종합지원시스템의 구축과 다원적평가와 분석이 가능하고, 비파괴검사에 의한 원전기기의 건전성 평가시 규제측면에서 기술적인 지원을 할 수 있는 고리 원전 PSI/ISI 데이터 베이스 구축과 프로그램을 개발하였다. 이 프로그램을 활용하면 현재까지 수행된 고리 원전 PSI/ISI의 수행현황과 지금까지 발견된 결함에 대한 조사분석이 가능하며, 향후 국내 PSI/ISI 결과의 자료분석이 가능한 전문가 시스템(expert system) 개발에 한단계 접근하게 되었다. 그리고, PSI/ISI에서 발견된 결함에 대한 조사분석 결과를 근거로 결함의 종류, 형태, 처리방법 등에 대한 자세한 분석을 통하여 국내 원전 PSI/ISI 결과의 확률론적 신뢰도 평가 또는 확률론적 안전성평가를 위한 결함검출확률곡선의 작성과 위험도에 근거한 가동중검사제도의 도입에 필요한 기초 자료를 제공하였다. 더 나아가 지금까지의 자료분석을 바탕으로 보다 경제적이며 신뢰성이 높은 PSI/ISI의 수행으로 원전 압력경계기기의 건전성과 신뢰성 확보 및 수명예측을 위한 기초자료를 제공하였다.