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A COMPARATIVE OVERVIEW OF THERMAL HYDRAULIC CHARACTERISTICS OF INTEGRATED PRIMARY SYSTEM NUCLEAR REACTORS
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  • A COMPARATIVE OVERVIEW OF THERMAL HYDRAULIC CHARACTERISTICS OF INTEGRATED PRIMARY SYSTEM NUCLEAR REACTORS
  • A COMPARATIVE OVERVIEW OF THERMAL HYDRAULIC CHARACTERISTICS OF INTEGRATED PRIMARY SYSTEM NUCLEAR REACTORS
저자명
NINOKATA. HISASHI
간행물명
Nuclear engineering and technology : an international journal of the Korean Nuclear Society
권/호정보
2006년|38권 1호|pp.33-44 (12 pages)
발행정보
한국원자력학회
파일정보
정기간행물|ENG|
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이 논문은 한국과학기술정보연구원과 논문 연계를 통해 무료로 제공되는 원문입니다.
서지반출

기타언어초록

This paper presents a review of small-to-medium-sized, pressurized-water-cooled nuclear power reactors whose major primary coolant systems are integrated into a reactor pressure vessel, the concepts categorized as Integrated Primary System Nuclear Reactors (IPSRs). Typical examples of these proposals of interest in this review are CAREM, SMART, IRIS and IMR, all of which are being aimed at the near term deployment. Emphasis is placed on thermal hydraulic aspects. A brief characterization of the IPSR concepts is made and comparisons of plant key parameters are shown. Discussions will follow for the core cooling under rated power conditions and natural circulation heat removal on the basis of the design data available in the public domain.