http://chineseinput.net/에서 pinyin(병음)방식으로 중국어를 변환할 수 있습니다.
변환된 중국어를 복사하여 사용하시면 됩니다.
제무성(Moo Sung Jae) 대한설비관리학회 1996 대한설비관리학회지 Vol.1 No.1
N/A The system unavailability is a probability that a system is in the failed state at time t, given that it jumped into the normal state at time zero. It is a function of human errors committed during maintenance and tests, component failure rates, surveilla
한국표준형 원전의 중대사고시 MACCS 코드를 이용한 위험성평가
황석원,제무성,Hwang, Seok-Won,Jae, Moo-Sung 대한방사선방어학회 2003 방사선방어학회지 Vol.28 No.3
Level 3 PSA(사고결말분석)는 원자력 발전소의 사고 시 누출된 방사성 핵종으로 인해 야기되는 환경 및 인체에 미치는 영향(공중위험도)을 평가하는 것이다. 본 논문에서는 원자력 발전소의 중대사고시 환경으로 방출되는 방사성물질의 방출특성과 그 결과로 인체에 미치는 영향에 대하여 확률론적 사고영향분석코드인 MACCS를 이용하여 평가하였다. 이러한 평가는 관련 변수들의 상대적 중요도를 파악하는데 유용할 뿐만 아니라 소외리스크(Offsite Risk)를 최소화시키기 위한 대책개발에 있어 중요한 지표가 될 수 있다. 특히 방출고도, 열 함량, 방출기간의 3가지 중요 변수를 선정하여, 이들 변수들의 변화에 따라 영향을 받는 조기사망자 수와 암 사망자 수의 변화를 분석하였다. 또한, 참조원전의 위험성 평가를 위하여 IPE(Individual Plant Examination)에서 제시된 STC(Source Term Category) 19가지 시나리오에 대한 각 사고별 빈도와 MACCS코드를 수행한 결과값을 이용하여 참조원전의 위험성 평가를 수행하였다. The Level 3 PSA being termed accident consequence analysis is defined to assess effects on health and environment caused by radioisotopes released from severe accidents of nuclear power plants. In this study consequence analysis on health effects depending on release characteristics of radioisotopes has been peformed using the 3 MACCS code in severe accidents. The results of this study may contribute to identifying the relative importance of various parameters occurred in consequence analysis as well as to assessing risk reduction accident management strategies. Especially three parameters for the purpose of consequence analysis, such as the release height, the heat content, and the duration time, are used to analyze the variation of early fatalities and latent cancer fatalities. Also, in this study risk assessment using the concept, 'products of uncertainty and consequences', has been performed using consequence of MACCS and frequency on source term category 19 scenarios from IPE (Individual Plant Examination) analysis.
제무성 한국산업안전학회 2000 한국안전학회지 Vol.15 No.4
In this paper, the human error contributions to the system unavailability are calculated and compared to the mechanical failure contributions. The system unavailability is a probability that a system is in the failed state at time t, given that it was the normal state at time zero. It is a function of human errors committed during maintenance and tests, component failure rates, surveillance test intervals, and allowed outage time. The THERP (Technique for Human Error Rate Prediction), generally called "HRA handbook", is used here for evaluating human error rates. This method treats the operator as one of the system components, and human reliability is assessed in the same manner as that of components. Based on the calculation results, the human error contribution to the system unavailability is shown to be more important than the mechanical failure contribution in the example system. It is also demonstrated that this method is very flexible in that it can be applied to any hazardous facilities, such as gas valve stations and chemical process plants.
제무성 한국산업안전학회 1999 한국안전학회지 Vol.14 No.4
a framework for assessing seismic safety is suggested in this paper. The concepts of requirement and achievement are used in this framework. The quantified correlation between requirement and achievement derived from two competing variables results in the unconditional frequency of exceeding a damage level. This framework can be applied to any other external safety assessment of nuclear power plants.
제무성 한국산업안전학회 2001 한국안전학회지 Vol.16 No.1
중대사고관리는 원전의 노심손상사고를 예방하거나 완화시키기 위하여 기존의 가용자원이나 시스템, 운전의 행위를 사용하는 것을 말한다. 제어실이나 기술지원반을 위하여 중대사고관리를 위하여 개발된 TRAIN(Training pRogram for Accident Management Program In Nuclear Power Plant)의 초기문자로 명명된 시스템을 본 논문에 소개하였다. TRAIN은 중대사고현상 KB(Knowledge Base)와 사고시나리오 KB, 제어도와 함께 사고관리 절차도 그리고 필요정보로 구성되어 있으며 제어실이나 기술지원반에게 중대사고의 현상 지식을 취득하게 하고, 발전소의 취약특성을 파악하게 하며, 상당한 스트레스하에서 주어진 문제를 해결하게 하는데 본 연구의 결과는 기여할것이다. Severe accident management can be defined as the use of existing and alternative resources, systems, and actions to prevent or mitigate a core-melt accident in nuclear power plants. TRAIN (Training pRogram for AMP In NPP), developed for training control room staff and the technical group, is introduced in this paper. The TRAIN composes of phenomenological knowledge base (KB), accident sequence KB and accident management procedures with AM strategy control diagrams and information needs. This TRAIN might contribute to training them by obtaining phenomenological knowledge of severe accidents, understanding plant vulnerabilities, and solving problems under high stress.
영향도를 이용한 새로운 인간신뢰도 분석방법의 개발 및 적용
제무성 한국산업안전학회 1998 한국안전학회지 Vol.13 No.1
Human errors performed during the operations have a dominant portion of the accidents. But the systematic human error evaluation methodology universally accepted is not developed yet. One of the difficulties in performing human reliability analysis is to evaluate the performance shaping factors which represent the characteristics and the circumstances in the discriminate manner. For assessing a specific human action more exactly, it is necessary to consider all of the PSFs at the same time which make an effect on the human action. In this paper, dynamic influence diagrams are introduced to model simultaneously their effects on the specific human action. And the human actions and their subsequent PSFs are categorized and classified as the complementary works. A new human error evaluation methodology using influence diagrams is developed. This methodology involves the categorization of PSFs and the PSFs quantification. The applied analysis results for the example task are shown for representative purposes. It is shown that this approach is very flexible in that it can be applied to any kind of actions.