• Proceedings of the Korea Society for Simulation Conference
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• 2000.04a
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• pp.161-167
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• 2000

주제어실의 경보계통은 중요한 발전소 변수의 비정상 상태 발생과 운전원의 관심을 요하는 기기상태의 변화에 대해 가시적/가정적 신호로 운전원에게 경고하는 역할을 담당하는 역할을 한다. 본 논문에서는 전력연구원에서 수행중인 '원자력 교육원 시뮬레이터 성능개선' 과제의 일부로 원자력교육원 2호기의 기준발전소인 영광 1호기의 디지털 경보설비 (IAS : Intelligent Annunciator System)의 구조와 이를 시뮬레이터 주컴퓨터 (Host Computer)상의 다이나믹 모델과 연동시켜 구현하는 방법론 및 구현된 경보감시계통에 대해 다루고 있다. 원자력교육원 2호기 경비감시계통은 Trend 모드, 그룹모드, 윈도우 모드, 조치사항 모드 및 조치사항 등록 모드 등 총 5개의 모드로 구성되어 있으며, 발생된 경보의 시간별/그룹별 출력, 경보창 에뮬레이션과 임의의 창에 대한 조치사항 출력, 새로운 경보에 대한 등록 및 삭제 등의 기능 구현이 가능하다. 또한 시뮬레이터에 대한 규제기관의 인허가가 중요한 현안으로 대두될 전망임에 따라 ANSI/ANS-3.5, Regulatory Guide 1.149 등 규제요건에서 제시하는 성능기준 및 검사기준을 만족하도록 설계함으로 향후 규제기관에 대한 인허가 획득을 대비하였다.

• Proceedings of the Earthquake Engineering Society of Korea Conference
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• 2003.03a
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• pp.110-117
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• 2003

The result of recent seismic hazard analysis indicates that the ground motion response spectra for Korean nuclear power plant site have relatively large high frequency acceleration contents. In the ordinary seismic fragility analysis of nuclear power plant structures and equipments, the safety margin of design ground response spectrum is directly used as a response spectrum shape factor. The effects of input response spectrum shape on the floor response spectrum were investigated by performing the direct generation of floor response spectrum from the ground response spectrum. The safety margin included in the design ground response spectrum should be considered as a floor response spectrum shape factor for the seismic fragility analysis of the equipments located in a building.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05a
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• pp.321-326
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• 1996

원자력발전소의 경보기능을 향상시키기 위하여 기존 경보기술 및 개량형 경보기술의 장단점을 평가하고 적용기술의 타당성을 검토하였다. 분석결과 기존 경보계통의 경우 경보생성논리의 한계성으로 인해 새로운 경보처리 알고리즘을 적용하는데 한계가 있는 것으로 나타났으며, 개량형 경보계통에서는 새로운 경보처리 알고리즘이 수용가능하나 제어실 설계에 따른 경보표시 기기의 배치 및 운용은 특정 알고리즘의 수용이 불가하거나 수정을 필요로 하는 것으로 나타났다. 본 평가분석은 개량형 경보처리기술 선정시 고려사항과 각 기술들의 적용 한계성을 보여주므로써 후속 원전 경보계통의 개발 및 구현시 활용될 수 있다.

• Proceedings of the Korea Information Processing Society Conference
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• 2009.11a
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• pp.911-912
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• 2009

핵연료교환기는 매일 일정량의 연료를 교체해 주어야 하는 중수로 원전의 특성상 작동이 빈번한 장비로 원활한 원자로 운전에 중요한 역할을 담당하고 있다. 이에 따라 핵연료교환기 점검시에 정비이력관리 및 기기 이상 진단 기능을 추가하여 점검의 신뢰성을 높이고자 한다. 진단 시스템은 제어신호 및 진단신호 저장을 통하여 점검 상태에 대한 이력 관리가 용이해지고, 신호처리를 이용한 이상 분석을 통하여 기존에 확인 할 수 없는 이상신호를 확인 할 수 있다.

• Journal of the Computational Structural Engineering Institute of Korea
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• v.26 no.2
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• pp.131-138
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• 2013

The high damping rubber bearings contributed to reduce a seismic force transmitted to upper structures, the material properties of rubber changes with time and the rubber with age-related degradation can affect the seismic response of structures and equipments. Therefore the seismic response of structure considering age-related degradation of isolators should be evaluated. In this paper, the stiffness and damping for isolators were defined using the aging data proposed by other researchers. The reactor containment building and the auxiliary building were selected to conduct the nonlinear analysis and the natural frequency, maximum responses, floor response spectrum(FRS) were evaluated with time using the four earthquakes with different frequency contents. According to the analysis results, the seismic responses are increased by the age-related degradation of isolators and the detail inspections should be conducted up to 20 years because it was presented that the change of FRS was high during this period.

• Journal of the Computational Structural Engineering Institute of Korea
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• v.27 no.5
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• pp.385-392
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• 2014

The isolators have been generally used to reduce a seismic force. If the isolators apply to the nuclear power plants(NPPs), the durability and capacity for the structures and equipments should be ensured during the life time. In this study, the long-term behavior of isolated NPPs was analyzed for ensuring the seismic safety. The properties of isolator due to the age-related degradation were analyzed. And the seismic behavior of isolated buildings was analyzed by considering the aging of rubber bearings in different temperature environments. According to the analysis results, the natural frequency of structures was increased with time. But the maximum acceleration and maximum displacement of isolated structures have not changed significantly. Although the damaged of structure did not occurred by aging of isolators, it was presented that the spectral acceleration at the target frequency of isolated structure increased with the temperature. Therefore the isolators in the isolated buildings should be carefully designed and manufactured considering the temperature-dependancy of rubber material.

• Journal of the Earthquake Engineering Society of Korea
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• v.9 no.1 s.41
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• pp.1-7
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• 2005

The optimal seismic retrofitting of NPP(Nuclear Power Plant) cabinet structures that contain seismic category 1 relays was studied in this paper. During earthquake event, the failure modes of relays are not appeared in form of structural failure, but are appeared in form of contact chatter of relay. Therefore, the retrofitting of cabinet has to be aimed at the reducing of the structural response, such as acceleration. In this study, the optimal characteristic values of dampers were searched by ${\mu}$-GA (micro-Genetic Algorithm) scheme for several installation patterns. To keep accuracy and efficiency of analysis, the structural models of cabinet were considered as a frame structure. The responses of structure were obtained inform of acceleration response spectra derived from the results of nonlinear time history analysis including damping nonlinearity. The objective function of the optimum procedure was constructed based on the maximum ratio of maximum spectral value and target GERS (General Equipment Ruggedness Spectra). The results show the good improvements of fitness for adequate retrofitting pattern. Especially, the improvements of fitness were remarkable when the values of damping exponents are low.

• Fire Science and Engineering
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• v.30 no.4
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• pp.20-26
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• 2016

When the fire takes place in Nuclear Powr Plants(NPPs), the reactor should achieve and maintain safe shut-down conditions and minimize the radioactive material released to the environment. The U.S. Nuclear Regulatory Commission (NRC) has issued numerous generic communications related to fire protection over the past 20 years, after it issued its requirements in the Fire Protection Rule set forth in Title 10, Section 50.48 of the Code of Federal Regulations (10 CFR 50.48) and Appendix R to the 10 CFR 50. The and Nuclear Energy Institute (NEI) has developed a Methodology for Risk Informed Fire Safe-Shutdown Analysis, which is related to the Deterministic Method for Multiple Spurious Operations solutions. The aim of this study was to identify, achieve, and maintain Post-Fire Safe-Shutdown of the Main Control Room (MCR) of the CANDU reactor, even though one train of the multiple Safety Structures, Systems, and Components (SCCs) fail by the technical specification and analysis method.

• Journal of Energy Engineering
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• v.23 no.3
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• pp.186-190
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• 2014

Nuclear Power Plants require the control ability of chemical condition (pH) because pH control during transient accident such as LOCA makes an able the fission product removal capability to be maintained, stress corrosion cracking of stainless steel equipment to be prevented and the production of hydrogen by aluminum and zinc to be minimized. An NPP is designed to control the pH of containment spray and sump coolant using the spray additives 30% NaOH in the event of loss of coolant accident. In this paper, the pH of sump coolant of an NPP during LOCA was analyzed and the fission products removal constant and decontamination factor were calculated according to Standard Review Plan 6.5.2 related to spray chemical conditions of pH. The calculated pH value of recirculation mode using the computer code corresponds to 8.09~9.67, which meets the chemical environment regulation requirements. The fission product removal capability caused by containment spray system is performed to provide input to radiation analysis.

• Journal of the Korea Academia-Industrial cooperation Society
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• v.17 no.6
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• pp.166-172
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• 2016

This paper deals with the seismic qualification of the reflective metal insulation for thermal shielding that is installed on the outer surfaces of the main equipment of the primary coolant system of a nuclear power plant. A small-scale model of the reactor pressure vessel, which has equivalent dynamic characteristics, was designed to be tested in domestic seismic testing facilities in the future. In this study, seismic analysis of the small-scale model installed with metal insulation was performed using equivalent static analysis and response spectrum analysis. The required Response Spectrum for main equipment of the primary coolant system of APR-1400 plant were considered to establish the enveloping response spectrum, which was applied to the seismic analysis model. The results from two seismic analysis methods were compared to show the structural adequacy of the metal insulator design against a safe shutdown earthquake. This study will form the basis for the seismic testing to support the seismic qualification of the reflective metal insulator.