• 대한인간공학회지
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• 제32권1호
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• pp.125-137
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• 2013

Objective: The aim of this study was to comprehend major concepts and flows that penetrate international guides or standards for developing a quantitative possibility measure of human errors that can be committed or omitted in nuclear power plants. Background: For a few past decades, lots of researchers have studied the effect of stress and/or fatigue which can result in human errors. Thus, this study was carried out on the assumption that much of them were summarized as an international guidelines or manuals, if any, for human error prevention. Method: A literal survey was conducted with materials and documentation published by international organizations related with safety and standardization, such as ISO, OSHA, NIOSH, NASA, and so on with special reference to human error prevention through management of work stress and fatigue as major Performance Shaping Factors. Results: International guides or management manuals on stress or fatigue management for human error prevention hardly were found, and most researches seemed to concentrate on one of them individually. Conclusion: There was few vestige of research that studied both concurrently. However, it was verified that not a few researches have been tried to develop quantitative measures to estimate probability or job characteristics for human error prevention and/or performance downgrading. Application: The results of this study would help to develop a causal model of human errors due to work stress and fatigue that can result in unexpected accidents in nuclear power plant.

• 에너지공학
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• 제8권2호
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• pp.285-292
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• 1999

한국표준원전의 원자로용기 단열재 설치시 설계인자에 대한 수치해석적 연구를 전산 유체유동 코드인 FLUENT를 이용하여 해석하였다. 단열재 두께 및 원자로용기 벽과 단열재의 내부표면간의 공간간격에 대한 인자에 대해서 연구를 수행했다. 또한 단열재 설치시 단열재판넬 사이의 틈새 간격 때문에 발생하는 chimney effect으로 인한 단열재의 성능저하를 평가하였다. 수치해석 결과 최적의 공간 간격 및 단열재 두께를 얻을 수 있었다.

• 한국전산구조공학회논문집
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• 제34권5호
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• pp.319-325
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• 2021

후쿠시마 원전사고 발생으로 다수기의 지진안전성에 관한 연구의 필요성이 부각되었다. 한 부지에 건설된 원자력발전소의 경우 유사한 지진응답을 보이기 때문에 적게나마 원자력발전소 SSCs간의 지진손상에 대하여 상관성이 존재하므로 합리적 지진안전성 평가를 위하여 지진손상 상관성을 고려하여야 한다. 본 연구에서는 쌍둥이 호기의 필수전원상실사건에 대하여 확률론적 지진안전성 평가를 수행하였다. 적절한 지진손상 상관계수를 도출하기 위하여 확률론적 지진응답해석을 수행하여 적용하였다. External Event Mensuration System 프로그램을 활용하여 다수기의 필수전원상실사건의 고장수목을 구성하여 지진취약도 및 지진리스크를 분석하였다. 또한 SSCs간의 지진손상 상관성을 완전독립 및 완전종속으로 고려하여 비교 분석을 수행하였다.

• 방사성폐기물학회지
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• 제21권3호
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• pp.329-345
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• 2023

This paper described a method for analyzing the structural performance of a metal container used for disposing radioactive waste generated during the decommissioning of a nuclear power plant, and numerical analysis results of a method for reinforcing the container. The containers to be analyzed were those that can be used in near-surface and landfill disposal facilities scheduled to be operated at the Gyeongju radioactive waste disposal facility. Structural reinforcement of the container was performed by lattice reinforcement, column reinforcement, and bottom plate reinforcement. Accordingly, a total of 14 reinforcement cases were modeled. The external force causing damage to the container was set equivalent to the impact of a 9-m fall, accounting for the height of the vault at the near-surface disposal facility. The reinforcement methods with a high contribution to the structural performance of the container were concluded to be lattice and column reinforcements.

• 비파괴검사학회지
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• 제29권5호
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• pp.466-472
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• 2009

고온, 고압의 원자력 배관 누설 판별을 위해 음향방출기법(AE)을 이용한 누설감지 시스템인 ALMS 기법이 적용되고 있다. 이 시스템은 단지 AE 센서로 전해진 신호의 RMS값을 이용하여 누설의 유무만을 판단할 뿐, 누설 발생시 누설부의 크기나 형태를 평가하는 것에는 어려움이 있었다. 따라서 본 논문에서는 이러한 문제를 해결하기 위하여 AE센서와 가속도센서를 동시에 이용한 이중 센서 시스템을 제안하였다. 빠른 학습 속도와 정확성을 위해 Levenberg-Marquardt 학습 알고리즘을 이용한 인공신경회로망을 적용시키고, 이를 통해 신뢰성 있는 분석 결과를 얻을 수 있다. 배관내 압력과 누설부의 크기와 모양에 따른 실험신호들을 학습시키고 그 판별 정확성을 확인하였다. 추가적으로 배관 두께에 따라 발생하는 파(wave)의 종류와 특성이 달라지는 것을 이론과 실험을 통하여 알아보았다.

• 대한인간공학회지
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• 제18권3호
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• pp.153-169
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• 1999

The design of nuclear control room is advancing toward totally computer based human system interfaces (HSI). Computer based interfaces offer the opportunity to provide improved support of operator performance, but if not properly deployed, can introduce new challenges. This paper reviews the Westinghouse AP-600 Human Factors Verification and Validation Plan selected for HSI evaluation model of Korea next generation nuclear control rooms. The AP-600 HSI evaluation model addressed 15 evaluation issues considering major activity class of operator and task complexity factors. This paper also describes the test procedures experimenters should follow to evaluate the addressed issues.

• 시스템엔지니어링학술지
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• 제16권2호
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• pp.16-26
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• 2020

Improving operator performance in complex and time-critical situations is critical to maintain plant safety and operability. These situations require quick detection, diagnosis, and mitigation actions to recover from the root cause of failure. One of the key challenges for operators in nuclear power plants is information management and following the control procedures and instructions. Nowadays Digital Twin technology can be used for analyzing and fast detection of failures and transient situations with the recommender system to provide the operator or maintenance engineer with recommended action to be carried out. Systems engineering approach (SE) is used in developing a digital twin for the CEDM system to support operator actions when there is a misalignment in the control element assembly group. Systems engineering is introduced for identifying the requirements, operational concept, and associated verification and validation steps required in the development process. The system developed by using a machine learning algorithm with a text mining technique to extract the required actions from limiting conditions for operations (LCO) or procedures that represent certain tasks.

• Nuclear Engineering and Technology
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• 제54권11호
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• pp.4170-4180
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• 2022

The task complexity (TACOM) measure was previously developed to quantify the complexity of proceduralized tasks conducted by nuclear power plant operators. Following the development of the TACOM measure, its appropriateness has been validated by investigating the relationship between TACOM scores and three kinds of human performance data, namely response times, human error probabilities, and subjective workload scores. However, the information reflected in quantified TACOM scores is still insufficient to determine the levels of complexity of proceduralized tasks for human reliability analysis (HRA) applications. In this regard, the objective of this study is to suggest criteria for determining the levels of task complexity based on logistic regression between human error occurrences in digitalized main control rooms and TACOM scores. Analysis results confirmed that the likelihood of human error occurrence according to the TACOM score is secured. This result strongly implies that the TACOM measure can be used to identify the levels of task complexity, which could be applicable to various research domains including HRA.

• Nuclear Engineering and Technology
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• 제55권6호
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• pp.2069-2087
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• 2023

In nuclear power plant (NPP) accidents, the containment is subject to high temperatures and high internal pressures, which may further trigger serious chain accidents such as core meltdown and hydrogen explosion, resulting in a significantly higher accident level. Therefore, studying the mechanical performance of a containment under high temperature and high internal pressure is relevant to the safety of NPPs. Based on similarity principles, the 1:3.2 scale model of a prestressed concrete containment vessel (PCCV) of a NPP was designed. The loading method, which considers the thermal-pressure coupling conditions, was used. The mechanical response of the PCCV was investigated with a simultaneous increase in internal pressure and temperature, and the failure mechanism of the PCCV under thermal-pressure coupling conditions was revealed.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2003년도 가을 학술논문집
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• pp.614-620
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• 2003

원자력연구소에서는 국내 원전에서 배출된 사용후핵연료를 IMEF M6 핫셀에서 건식 재가공하여 건식공정 산화물핵연료를 개발하였다. 개발된 핵연료의 성능을 검증하기 위해서는 실제 상용로와 동일한 고온고압 조건하에서 조사시험이 필요하나 국내에는 이러한 조사시설을 갖추지 못하고 있으므로 핵연료 성능의 검증이 어렵던 차에 한$\cdot$카$\cdot$미 IAEA간의 국제공동연구 과제진도회의에서 AECL측은 중성자비를 받지 않고 캐나다 NRU에서 건식공정 산화물핵연료를 조사시험을 할 수 있다고 제안하였다. NRU 조사시험을 하고자 하는 핵연료는 건식공정 산화물핵연료봉 10개(약 6kgU)이며 운반물 분류등급에 따라 제7종 위험물로 핵분열성물질에 해당한다. 일반적으로 소량의 방사성물질을 운반할 경우에는 비용뿐 아니라 수송기간 측면에서 항공수송이 선박수송에 비해 유리한 것으로 알려져 있어 항공기를 이용한 건식공정 산화물핵연료의 해외 수송방안을 검토하였다. 검토결과, 현재 건식공정 산화물핵연료봉 10개를 운반할 수 있는 적절한 항공수송용 수송용기가 없어 항공수송이 불가능한 것으로 조사되었다. 선박을 이용한 해외 수송방안은 가능하나 이 경우에는 전용선박을 사용해야 함으로 비용이 많이 수요되는 것으로 분석되었다.