Validation of WIMS-AECL Against Actual Operating History: Core Follow of Point Lepreau Nuclear Generating Station with POWDERPUFS-V and WIMS-AECL

Abstract

A one-year period of operating history of the Point Lepreau CANDU-6 Nuclear Generating Station has been simulated using the WIMS-AECL lattice-cell code with the RFSP reactor-core code. Overall, agreement between these new results using the WIMS-AECL lattice code, old results using the POWDERPUFS-V lattice code, and measured in-core detector values is good. about 6 to 7 mk in reactor eigenvalue, 2 to 3% in vanadium detector signals, and 1 to 2% in global reactor thermal neutron flux tilts.