• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1999년도 추계학술발표회요약집
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• pp.380.2-380
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• 1999

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1999년도 추계학술발표회요약집
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• pp.388.1-388
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• 1999

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2018년도 추계학술논문요약집
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• pp.45-46
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• 2018

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2017년도 추계학술논문요약집
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• pp.39-40
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• 2017

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2017년도 춘계학술논문요약집
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• pp.29-30
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• 2017

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1996년도 춘계학술발표회논문집(2)
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• pp.467-472
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• 1996

This study discusses special aspects of severe accident related recriticality modeling and analysis in the Advanced Neutron Source (ANS) reactor.$^{1, 2)}$ The analytical comparison of three elements core to former two elements case is conducted including evaluation of suitable nuclear cross-section sets to account for the effects of system configulation, fuel and moderator mixture temperature, material dispersion and the other thermal-hydraulics. Three elements core ANS reactor is the alternative core design which was proposed as a modified core design, with three fuel elements instead of two, that would allow operation with only 50% enriched uranium (former uranium fuel is the baseline design value of 93%) A comprehensive test matrix of calculations to evaluate the threat of a criticality event in the ANS is described. Strong dependencies still on geometry, material constituents, and thermal-hydraulic conditions are verified. Therefore, the concepts of mitigative design features are qualified.d.

• 대한인간공학회지
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• 제16권3호
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• pp.77-87
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• 1997

This paper describes the developement of a Design Issue Management System (DIMS). Although human factors engineering has been recognized as one of the critical activities in the design of man-machine system, it has been hardly successful nor effective in practice to cope with the hyman factors requirements by regulations. For supporting the human factors engineering in nuclear power plants, DIMS ahs three major modules : Design Requirements Data Base, Design Issue Tracking System, Issue Evaluation Support System. These modules function as formal verification architects that the licensing authority requests for verifying the safety of the equip- ment and facilities in nuclear power plants. An example application to an operator support system, named Critical Function Monitoring System, during its independent review of the human factors shows the usage and the benefit of DIMS.

• 대한전기학회:학술대회논문집
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• 대한전기학회 1991년도 하계학술대회 논문집
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• pp.734-737
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• 1991

본 고는 공학적 안전설비 작동계통 보조계전기 캐비넷의 설계과정을 위하여 작성되었다. 공학적 안전설비 작동계통 설계는 순차적인 과정을 밟아서 진행이 되므로, 설계담당자(Cognizant Engineer)는 그 작업순서를 이해하여야 하며, 각 과정마다 필요한 자료들과 생산해야될 결과물들을 정확히 파악하여야만 설계가 원활히 수행될 수 있다. 또한, 설계과정은 많은 연계 업무가 있으므로, 서로 주고받아야 할 자료들의 종류 및 그 시기를 예상할 수 있어야 한다. 그리하여, 본 내용에서는 공학적 안전설비 작동계통 보조전기 캐비넷의 특성에 따라 연계요건서, 설계시방서 및 개념적인 도면을 중심적으로 기술하였으며, 기기설계(Component Design)와 제작설계(Manufacturing Engineering) 및 현장지원(Field Supports)은 아직까지도 미비한 점이 많으나, 담당자(Cognizant Engineer)가 아는 바대로 작성하였다.

• 시스템엔지니어링학술지
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• 제6권1호
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• pp.47-52
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• 2010

Human Factors Engineering (HFE) for Main Control Room (MCR) of Nuclear Power Plant (NPP) has been applied to optimize the design and operation of Man-Machine Interface (MMI) between operators and their equipment in consideration of physical, psychological and cognitive aspects. However, it has been observed that operators complain about environmental discomfort in the MCR since the operators in the MCR experience excessive stress due to the environmental factors such as inappropriate interior and lighting system. Since the HFE is an essential factor for the high fidelity performance of operators in the MCR, the adequate MCR environment design with HFE rules and guidelines is as much important to enhance the operability and reliability of the MCRs. Therefore, there has been a strong need to design a pleasant environment for the MCR to improve human performance of the operators.

• Nuclear Engineering and Technology
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• 제37권6호
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• pp.605-610
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• 2005

A method to estimate the relative sensitivity of a self-powered rhodium detector for an upcoming cycle is developed by combining the rhodium depletion data from a nuclear design with the site measurement data. This method can be used both by nuclear power plant designers and by site staffs of Korean standard nuclear power plants for determining which rhodium detectors should be replaced during overhauls.