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Martin, William R.; Lee, John C.
University of Michigan (United States). Funding organisation: US Department of Energy (United States)2009
University of Michigan (United States). Funding organisation: US Department of Energy (United States)2009
AbstractAbstract
[en] Monte Carlo capability has been combined with a production LWR lattice physics code to allow analysis of high temperature gas reactor configurations, accounting for the double heterogeneity due to the TRISO fuel. The Monte Carlo code MCNP5 has been used in conjunction with CPM3, which was the testbench lattice physics code for this project. MCNP5 is used to perform two calculations for the geometry of interest, one with homogenized fuel compacts and the other with heterogeneous fuel compacts, where the TRISO fuel kernels are resolved by MCNP5.
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30 Dec 2009; 73 p; FC07-06ID14745; Also available from OSTI as DE00970985; PURL: https://www.osti.gov/servlets/purl/970985-t08Vm4/; doi 10.2172/970985
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