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서지반출
DEVELOPMENT OF MARS-GCR/V1 FOR THERMAL-HYDRAULIC SAFETY ANALYSIS OF GAS-COOLED REACTOR SYSTEMS
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  • DEVELOPMENT OF MARS-GCR/V1 FOR THERMAL-HYDRAULIC SAFETY ANALYSIS OF GAS-COOLED REACTOR SYSTEMS
  • DEVELOPMENT OF MARS-GCR/V1 FOR THERMAL-HYDRAULIC SAFETY ANALYSIS OF GAS-COOLED REACTOR SYSTEMS
저자명
LEE. WON-JAE,JEONG. JAR-JUN,LEE. SEUNG-WOOK,CHANG. JONGHWA
간행물명
Nuclear engineering and technology : an international journal of the Korean Nuclear Society
권/호정보
2005년|37권 6호|pp.587-594 (8 pages)
발행정보
한국원자력학회
파일정보
정기간행물|ENG|
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이 논문은 한국과학기술정보연구원과 논문 연계를 통해 무료로 제공되는 원문입니다.
서지반출

기타언어초록

In an effort to develop a thermal-hydraulic (TH) safety analysis code for Gas-cooled Reactors (GCRs), the MARS code, which was primarily developed for TH analysis of water reactor systems, has been extended here for application to GCRs. The modeling requirements of the system code were derived from a review of major processes and phenomena that are expected to occur during normal and accident conditions of GCRs. Models fur code improvement were then identified through a review of existing MARS code capability. Among these, the following priority models necessary fur the analysis of limiting high and low pressure conduction cooling events were evaluated and incorporated in MARS-GCR/V1 : 1) Helium (He) and Carbon Dioxide ($CO_2$) as main system fluids, 2) gas convection heat transfer, 3) radiation heat transfer, and 4) contact heat transfer models. Each model has been assessed using various conceptual problems for code-to-code benchmarks and it was demonstrated that MARS-GCR/V1 is capable of capturing the relevant phenomena. This paper describes the models implemented in MARS-GCR/V1 and their verification and validation results.