• Title/Summary/Keyword: Kori-1 nuclear power plant

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PERIODIC SAFETY REVIEW ON KORI UNIT 1 (고리 1호기 주기적안전성 평가)

  • Kim, Tae-Ryong
    • Proceedings of the Korea Society for Energy Engineering kosee Conference
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    • 2003.05a
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    • pp.403-414
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    • 2003
  • Periodic safety review on Kori Unit 1 has been successfully done for the first time in Korea. 11 safety factors of the review were fully evaluated in accordance with the domestic legal system. Although it is the oldest nuclear power plant in Korea, Kori Unit 1 was found to have maintained good operating conditions and continuously enhanced its safety by implementing post-TMI action plans and other safety issues, such as replacing steam generators and process/control system. It can be therefore confirmed that safe operation of Kori Unit 1 is guaranteed until next periodic safety review. Nevertheless, some corrective action items were recommended to enhance further its safety level, such as equipment qualification, additional ageing management program, strengthening of some procedures related to administration and human factor. The results of PSR can be utilized for the continued operation beyond the design life as long as the plant safety is maintained and improved. Experiences of the PSR on Kori Unit 1 can be also applied to PSR on other plants.

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Non-Integrated Standalone Test of An Nuclear Steam Supply System Thermal-Hydraulic Program for the Westinghouse Type Nuclear Power Plant Simulator Using A Best-Estimate Code (최적 계통분석 코드를 이용한 웨스팅하우스형 원자력발전소 시뮬레이터용 핵 증기 공급 계통 열수력 프로그램 독자평가 및 시험)

  • 서인용;이명수;이용관;서재승;권순일
    • Proceedings of the Korea Society for Simulation Conference
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    • 2004.05a
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    • pp.101-108
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    • 2004
  • KEPRI has developed an Nuclear Steam Supply System(NSSS) thermal-hydraulics simulation program (called ARTS-KORI), based on the best-estimate system code, RETRAN, as a part of the development project for the KORI unit 1 Nuclear Power Plant Simulator. A number of code modifications, such as simplifications and removing of discontinuities of the physical correlations, were made in order to change the RETRAN code as an nuclear Steam Supply System thermal-hydraulics engine in the simulator. Some simplified models and a backup system were also developed. This paper briefly presents the results of non-integrated standalone test of ARTS-KORI.

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TECHNICAL EVALUATION OF THE CONTINUED OPERATION OF NPP

  • Kim, Tae-Ryong;Jin, Tae-Eun
    • Nuclear Engineering and Technology
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    • v.40 no.4
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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.

Thermal-Hydraulic Analysis Methodology of Nuclear Power Plant Steam Generator (원전 증기발생기 열유동 해석법)

  • Choi Seok-Ki;Kim Seong-O;Choi Hoon-Ki
    • Journal of computational fluids engineering
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    • v.7 no.2
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    • pp.43-52
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    • 2002
  • This paper presents the numerical methodology of ATHOS3 code for thermal hydraulic analysis of steam generators in nuclear power plant. Topics include porous media approach, governing equations, physical models and correlations for solid-to-fluid interaction and heat transfer, and numerical solution scheme. The ATHOS3 code is applied to the thermal hydraulic analysis of steam generator in the Korea Kori Unit-1 nuclear power plant and the computed results are presented

Analysis on the Pigment Composition of Phytoplankton Assemblages using HPLC (High Performance Liquid Chromatography) in the Adjacent Waters of Nuclear Power Plants in Spring

  • Choi, Hyu-Chang;Kang, Yeon-Shik;Choi, Joong-Ki;Song, Tae-Yoon;Yoo, Man-Ho
    • Journal of the korean society of oceanography
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    • v.39 no.4
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    • pp.234-242
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    • 2004
  • The pigment composition and concentration of phytoplankton assemblages using HPLC in the adjacent waters of four nuclear power plants (Yonggwang, Kori, Wolsong and Ulchin) were investigated during the spring blooming in 2004. The mean concentration of chlorophyll a ranged from 563.8 to 2,949.0ng $l^{-1}$, with the lowest concentration at Kori and the highest concentration at Wolsong. Among the carotenoids, the amounts of fucoxanthin and chlorophyll $C_2$ were relatively higher than those of other pigments in the study site. As minor pigments, zeaxanthin, chlorophyll b, 19'-butanoyloxyfucoxanthin, diadinoxanthin, 19'-hexanoyloxyfucoxanthin, chlorophyll $C_3$ and peridinin were detected. The results of pigment composition and concentration showed that diatoms had an important proportion of phytoplankton community when a spring bloom occurred. Cyanobacteria was present relatively low density at the Wolsong and the green alga such as chlorophytes and prasinophytes were abundant at the Yonggwang and Kori, while dinoflagellates characterized by peridinin were common at Ulchin and Kori. The pigment composition and concentration of phytoplankton after passing through the cooling-water system of nuclear power plant were highly variable. No distinct trend of the change of each pigment composition and amount was detected but the variation of fucoxanthin and chlorophyll $C_2$ highly coupled with that of chlorophyll a. We pointed out that the diatom controlled the overall variation of phytoplankton biomass during the spring season.

A Strategy for Kori Unit 1 Pressure Vessel Fluence Reduction through a Modification of Outer Assembly Configuration Using Monte Carlo Analysis

  • Kim, Jae-Cheon;Kim, Jong-Kyung;Kim, Jong-Oh
    • Proceedings of the Korean Nuclear Society Conference
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    • 1997.05b
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    • pp.515-519
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    • 1997
  • The purpose of this study is to reduce the fast neutron fluence at the reactor pressure vessel(RPV) and to provide a basis for plant-life extension. In this study, different neutron absorbers were employed in the core outer assemblies of Kori Unit 1 Cycle 14. The modified assemblies were used to calculate fast neutron fluence at the RPV and to evaluate reduction of outer assembly power and total power in core. By comparison with the case of no suppression fixture, the fast neutron fluence of a case with two rows stainless steel around the assembly with natural uranium pins is decreased by 85.8%. It is noted that the modification of outer assembly is more efficient than the previous low leakage loading pattern (LLLP) applied to Kori Unit 1. Also, compared fast neutron fluence in Cycle 1 with Cycle 14, fast neutron fluence at the RPV between Cycle 1 and Cycle 14 is not significantly different. It is found that LLLP applied to the Kori Unit 1 has not contributed to fast neutron fluence reduction at the RPV.

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