Proceedings of the KSME Conference (대한기계학회:학술대회논문집)

The Korean Society of Mechanical Engineers (대한기계학회)
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Structural Concept Design of KALIMER-600 Sodium Cooled Fast Reactor

소듐냉각 고속로 KALIMER-600 원자로 구조 개념설계

  • 이재한 (한국원자력연구원, 고속로개발그룹) ;
  • 박창규 (한국원자력연구원, 고속로개발그룹) ;
  • 김종범 (한국원자력연구원, 고속로개발그룹) ;
  • 구경회 (한국원자력연구원, 고속로개발그룹)
  • Published : 2007.05.30
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Abstract

KALIMER-600 is a sodium cooled fast reactor with a fast spectrum neutron reactor core. The NSSS design has three heat transport systems of a PHTS (Primary Heat Transport System), a IHTS (Intermediate Heat Transport System) and a SGS (Steam Generation System). PHTS is a pool type and has a large amount of sodium in the pool. The mechanical design targets are maintaining the enough structural integrity for a seismic load of SSE 0.3g and the thermal and mechanical loads by the high temperature environments and an economical competitiveness when compared with other reactor types.

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