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DEVELOPMENT OF MARS-GCR/V1 FOR THERMAL-HYDRAULIC SAFETY ANALYSIS OF GAS-COOLED REACTOR SYSTEMS  

LEE WON-JAE (Korea Atomic Energy Research Institute)
JEONG JAR-JUN (Korea Atomic Energy Research Institute)
LEE SEUNG-WOOK (Korea Atomic Energy Research Institute)
CHANG JONGHWA (Korea Atomic Energy Research Institute)
Publication Information
Nuclear Engineering and Technology / v.37, no.6, 2005 , pp. 587-594 More about this Journal
Abstract
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.
Keywords
Gas-Cooled Reactor; Thermal Hydraulic; Safety; MARS; Heat Transfer; Gas Property;
Citations & Related Records
Times Cited By KSCI : 2  (Citation Analysis)
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