Assessment of TRITON and PARCS for Full-Core MOX Fuel Calculations

摘要

The neutron physics of MOX fuels mayrepresent a challenge to existing computational tools.However, the more rigorous treatment of neutrontransport available within NEWT, coupled with theaccuracy of ORIGEN-S depletion capabilities andSCALE self-shielding calculations within TRITONdrivenlattice physics analyses, provides a rigorousfirst-principles approach for calculation of crosssections for such fuel designs. Although not initiallydeveloped to be a general production tool for MOXanalyses, the TRITON sequence provides a rigorousphysics treatment of MOX fuel transport anddepletion, providing improved insight into thephysics of such systems. It is anticipated that thisknowledge will allow improvement in other analysismethods and/or data to help meet the needs of futureMOX-fueled cores.