Development of Safety Analysis Codes and Experimental Validation for a Very High Temperature Gas-Cooled Reactor - FY-05 Annual Report
作者： Chang Oh
DOI: 10.2172/911255
关键词:
摘要: The RELAP5-3D© computer code is being improved for the analysis of very high temperature gas-cooled reactors. Diffusion and natural circulation can be important phenomena in reactors following a loss-of-coolant accident. Recent improvements to include addition models that simulate pressure loss across pebble bed molecular diffusion. These were assessed using experimental data. diffusion model was data from inverted U-tube experiments. code’s capability air through NACOK facility. calculated results reasonable agreement with measured values.
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