• Title/Summary/Keyword: KNGR

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A Study of Cooldown Performance of Shutdown Cooling System of Korea Next Generation Reactor (차세대 원자로 정지냉각계통의 냉각 성능에 대한 연구)

  • 유성연;이상섭
    • Journal of Energy Engineering
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    • v.8 no.4
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    • pp.525-532
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    • 1999

  • The standardized Korea Next Generation Reactor (KNGR) NSSS has developed in the basis of the ABB-CE System 80+ design concept. In this study, several regulatory requirements for the KNGR shutdown cooling system (SCS) operation are investigated. The purpose of this study is to establish the technical self-reliance for SCS design by supporting fundamental data such as SDCHX effective area and reactor CCW flow rate. Thermal power of KNGR would be increased to about 4,000 $MW_{th}$ in comparison with thermal power 2.825 $MW_{th}$ of UCN 3&4, therefore, SCS design data shall b recalculated by using the KDESCENT Code, which could evaluate cooling capability of SCS. It is found that SCS minimum flow rate is able to remove the primary sensible heat. Reviewing the major components such as heat exchanger, pump, value, and operating procedure, it is concluded as follows.

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전자식 절차서 시스템의 개념 및 개발방향의 설정

  • 허태영;정경훈
    • Proceedings of the Korean Nuclear Society Conference
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    • 1996.11a
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    • pp.197-202
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    • 1996

  • 현재 운영중인 문서식 절차서 시스템과 개발이 완료된 전자식 절차서 시스템인 Maiden Reactor Project의 COPMA를 분석하여 COPMA가 가지고 있는 기능들에 대한 장, 단점을 파악, 평가하였으며, 그 평가를 이용하여 KNGR 전자식 절차서 시스템의 상위개념을 설정하고, 전자식 절차서 시스템이 필수적으로 가져야 하는 기능들을 도출하였다.

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