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자료유형
학술저널
저자정보
저널정보
한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제37권 제6호
발행연도
2005.1
수록면
587 - 594 (8page)

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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 for code improvement were then identified through a review of existing MARS code capability. Among these, the following priority models necessary for 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 (CO2) 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 MARSGCR/ V1 and their verification and validation results.

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