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FEASIBILITY OF AN INTEGRATED STEAM GENERATOR SYSTEM IN A SODIUM-COOLED FAST REACTOR SUBJECTED TO ELEVATED TEMPERATURE SERVICES
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  • FEASIBILITY OF AN INTEGRATED STEAM GENERATOR SYSTEM IN A SODIUM-COOLED FAST REACTOR SUBJECTED TO ELEVATED TEMPERATURE SERVICES
  • FEASIBILITY OF AN INTEGRATED STEAM GENERATOR SYSTEM IN A SODIUM-COOLED FAST REACTOR SUBJECTED TO ELEVATED TEMPERATURE SERVICES
저자명
Koo. Gyeong-Hoi,Lee. Jae-Han
간행물명
Nuclear engineering and technology : an international journal of the Korean Nuclear Society
권/호정보
2009년|41권 8호|pp.1115-1126 (12 pages)
발행정보
한국원자력학회
파일정보
정기간행물|ENG|
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기타
이 논문은 한국과학기술정보연구원과 논문 연계를 통해 무료로 제공되는 원문입니다.
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기타언어초록

As one of the ways to enhance the economical features in sodium-cooled fast reactor development, the concept of an integrated steam generator and pump system (ISGPS) is proposed from a structural point of view. And the related intermediate heat transfer system (IHTS) piping layout compatible with the ISGPS is described in detail. To assure the creep design lifetime of 60 years, the structural integrity is investigated through high temperature structural evaluation procedures by the SIE ASME-NH computer code, which implements the ASME-NH design rules. From the results of this study, it is found that the proposed ISGPS concept is feasible and applicable to a commercial SFR design.