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ASSESSMENT OF A NEW DESIGN FOR A REACTOR CAVITY COOLING SYSTEM IN A VERY HIGH TEMPERATURE GAS-COOLED REACTOR
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  • ASSESSMENT OF A NEW DESIGN FOR A REACTOR CAVITY COOLING SYSTEM IN A VERY HIGH TEMPERATURE GAS-COOLED REACTOR
  • ASSESSMENT OF A NEW DESIGN FOR A REACTOR CAVITY COOLING SYSTEM IN A VERY HIGH TEMPERATURE GAS-COOLED REACTOR
저자명
PARK. GOON-CHERL,CHO. YUN-JE,CHO. HYOUNGKYU
간행물명
Nuclear engineering and technology : an international journal of the Korean Nuclear Society
권/호정보
2006년|38권 1호|pp.45-60 (16 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

Presently, the VHTGR (Very High Temperature Gas-cooled Reactor) is considered the most attractive candidate for a GEN-IV reactor to produce hydrogen, which will be a key resource for future energy production. A new concept for a reactor cavity cooling system (RCCS), a critical safety feature in the VHTGR, is proposed in the present study. The proposed RCCS consists of passive water pool and active air cooling systems. These are employed to overcome the poor cooling capability of the air-cooled RCCS and the complex cavity structures of the water-cooled RCCS. In order to estimate the licensibility of the proposed design, its performance and integrity were tested experimentally with a reduced-scale mock-up facility, as well as with a separate-effect test facility (SET) for the 1/4 water pool of the RCCS-SNU to examine the heat transfer and pressure drop and code capability. This paper presents the test results for SET and validation of MARS-GCR, a system code for the safety analysis of a HTGR. In addition, CFX5.7, a computational fluid dynamics code, was also used for the code-to-code benchmark of MARS-GCR. From the present experimental and numerical studies, the efficacy of MARS-GCR in application to determining the optimal design of complicated systems such as a RCCS and evaluation of their feasibility has been validated.