Comparative Study of WIMS-AECL and MCNP ＆ MCBurn

This work,using WIMS-AECL,MCNP-4B and MCBurn codes,has calculated the criticality and burnup problems of a series of benchmarks and advanced CANDU lattices,including all-uranium and thorium-based fuels.WIMS-AECL uses ENDF/B-V and ENDF/B-VI nuclear data library separately.Comparison manifests that for benchmark,both B-V and B-VI can lead to good results and B-V is better;for all-uranium fuel of ACR and thorium-based fuel of ACR,WIMS-AECL with B-V is a better choice.