• 한국소음진동공학회:학술대회논문집
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• 한국소음진동공학회 2001년도 춘계학술대회논문집
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• pp.688-694
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• 2001

The 84m discharge line of moisture separator reheater(MSR) in Kori-2 had been suffered by excessive vibration from the beginning of power generation. In 1993, a complementary measure was taken to reduce the vibration level by adding several supports in the MSR pipeline. However, the piping vibration was beyond the allowable limit and an appropriate countermeasure was required to prevent the fatigue failure of the pipeline from the abnormal vibration. In this study, the vibrational characteristics of MSR pipeline and the countermeasure for abnormal vibration was investigated. Among the several vibration reduction methods, piping layout change by smoothing the pipeline was applied to the MSR pipeline in Kori-2. Applying the countermeasure, the vibration level was found to dramatically reduce from 17cm/sec to l.0cm/sec at the full-power operation condition.

• Nuclear Engineering and Technology
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• 제19권1호
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• pp.42-50
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• 1987

고리 2호기와 원자력 안전센터 상황실을 연결하는 Nuclear Data Link System에 대하여 기술하였다. 특히 선정된 원자력 안전변수, Data Link용 Pseudo-Network 소프트웨어, 관련장비들의 입출력 기능 및 전송된 자료의 영상화 등의 내용을 포함하였다. 아울러 현재까지 수행해온 고리 1,2,5,6호기에 대한 비상대응 설비의 설계 내용과 ERF/SPDS 하드웨어 및 소프트웨어 국산화 연구 방향을 제시하였다.

• Journal of Radiation Protection and Research
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• 제28권4호
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• pp.349-351
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• 2003

To ensure the safety of the currently operating nuclear power plant, the Periodic Safety Review program has been conducted. In PSR program, the cumulative behavior of the radionuclide that might be released from the power plant is addressed. The Cs-137 in soil around Kori nuclear power plant was investigated. The soil sample was analyzed and compared with the reference area. The model calculation explained the depth profile of Cs-137.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2008년도 추계학술대회A
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• pp.88-93
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• 2008

Weld overlay is one of the residual stress mitigation method which arrest crack. An overlay weld sued in this manner is termed a preemptive weld overlay(PWOL). PWOL was good for distribution of residual stress of dissimilar metal weld(DMW) by previous research. Because range of overlay welding is wide relatively, residual stress distribution on PWR is affected by welding sequence. In order to examine the effect of welding sequence, PWOL was applied to a specific DMW of KORI nuclear power plant by finite element analysis method. As a result, the welding direction that from nozzle to pipe is better good for residual stress distribution on PWR.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1997년도 추계학술발표회논문집(1)
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• pp.437-442
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• 1997

To determine the optimum pressurizer water level during normal operation for Kori unit 1, performance and safety analysis are peformed. The methodology is developed by evaluating "decrease in secondary heat removal" events such as Loss of Normal Feedwater accident. To demonstrate optimum pressurizer level setpoint, RETRAN-03 code is used for performance analysis. Analysis results of RETRAN following reactor trip are compared with the actual plant data to justify RETRAN code modelling, The results of performance and safety analyses show that the newly established level setpoints not only improve the performance of pressurizer during transient including reactor trip but also meet the design bases of the pressurizer volume and pressure. pressure.

• Nuclear Engineering and Technology
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• 제10권1호
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• pp.13-25
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• 1978

1970년 12월에서 1976년 12월 사이의 6년간 고리 원자력발전소 주변 환경에서 채취한 시료에 대하여 환경방사능을 측정조사하였다. 1976년에 채취한 공기미진에서 진알파 방사능과 1970년 12월에서 1976년 12월 사이에 채취한 시료인 토양, 물, 공기미진, 낙진, 솔잎, 빗물과 여런 식품시료에 페하여 전베타 방사능을 측정하였다. 시금치, 배추, 보리, 쌀, 뱀장어, 조기, 미역, 파해 및 우유 중에 함유된 스트론튬-90및 세시움-137 방사능은 방사화학적으로 분석하여 측정하였고 정수, 하천수, 바닷물 중의 트리튬도 전해법으로 농축하여 그 방사능을 측정하였다.

• Nuclear Engineering and Technology
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• 제50권6호
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• pp.963-970
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• 2018

The U.S. Nuclear Regulatory Commission, Regulatory Guide 1.20 needs to perform a comprehensive vibration assessment program for reactor internals during preoperational and startup testing for nuclear power plants and extended power uprate. Although the measurement program is one of the core programs, it is rarely carried out except for a first-of-a-kind or a unique design. This article describes measurement results of vibration and stress for the comprehensive vibration assessment program for an APR-1400 reactor internals. The measurement was performed at an upper guide structure during the pre-core hot functional test of Shin Kori unit 4 reactor internals because the Shin Kori unit 3 and 4 are the first construction project for the APR-1400, and the upper guide structure assembly was to design change compared with the valid prototype. We confirmed that all measured results are within the test acceptance criteria. It means that the structural integrity of the APR-1400 reactor internals was secured for the flow-induced vibration.

• 한국시뮬레이션학회:학술대회논문집
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• 한국시뮬레이션학회 2003년도 추계학술대회 및 정기총회
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• pp.159-164
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• 2003

DCS (Distributed Control System) is adapted in the most fossil power plant in our country but that is not true in the nuclear power plant (NPP) because of the safety problem. KEPRI has developed many simulators for the training of the operators working in power plants. With this accumulated high technology we are developing a DCS simulator for the performance verification of the developed DCS for the make-up demin-water treatment system of Kori #3&4. In this paper we explain how we develop the system model and show a simulation result.

• Nuclear Engineering and Technology
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• 제40권4호
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• pp.277-284
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• 2008

Recently, the long-term operation of a nuclear power plant beyond its licensed term has become a worldwide trend as long as the safety of the plant is maintained in the extended period. Kori Unit 1, the oldest PWR in Korea, is the foremost example of this type of long-term operation in Korea. Comprehensive technical evaluation of the long-term operation of this plant was completed to confirm the overall safety of the plant. The technical evaluation included a review of PSR results, an assessment on aging management programs and time limited aging analyses, and a statement of radiological impact on the environment. Based on all of the results of the technical evaluation activities, Kori Unit 1 was approved to operate for an additional 10 years beyond its original design life of 30 years.

• 방사성폐기물학회지
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• 제19권2호
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• pp.177-186
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• 2021

Radioactive materials from nuclear power facilities can be released into the atmosphere through various channels. Recently, the dispersion of radioactive materials has become critical issue in Korea after Kori Unit 1 and Wolsong Unit 1 were permanently shut down. In this study, annual atmospheric dispersion factors were compared based on the continuous release and purge release using the XOQDOQ computer program, a method for calculating atmospheric dispersion factors at commercial nuclear power stations. The meteorological data analyzed in this study was based on the Shin Kori nuclear power meteorological tower which has the largest operating nuclear power plants in Korea, for three years (from 2008 to 2010). The analysis results of the dispersion factor of the radioactive material release obtained using the XOQDOQ program showed that the difference between the continuous release and purge release was within two times. This study will be valuable helpful for revealing the uncertainty of the predictive atmospheric dispersion factor to achieve regulation.