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Roh, Gyu Hong; Kim, Yong Hee; Kim, Won Young; Park, Joo Hwan
Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)2009
Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)2009
AbstractAbstract
[en] Using WIMS-AECL code, which is 2-dimensional lattice core used in CANDU physics calculation, the discharge burnup of the natural uranium loaded CANFLEX-43 fuel bundle was evaluated by comparing the discharge burnup of standard 37 element fuel bundle. When the discharge burnup of the standard 37 element fuel is 7,200 MWd/MTU, that of the CANFLEX 43 fuel bundle was evaluated as 7,077 MWd/MTU, by applying the same lattice conditions for both fuel bundles
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Nov 2009; 40 p; Also available from KAERI; 8 refs, 2 figs, 8 tabs
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