Mathematics and Computation, 2005
Three dimensional whole-core transport code DeCART has been developed to include the
characteristics of a numerical reactor to replace a part of an experiment. This code can be a
substitute for the conventional 2-step procedure of the reactor physics analysis. This code adopts
the deterministic method for simulating the neutron behavior with the least amount of
assumptions and approximations. This neutronic code already included the capability for the
transient and thermal hydraulic feedback calculations. A depletion module has been
implemented into the DeCART code to predict the depleted composition in a fuel, which adopts
the exponential matrix method of ORIGEN-2. Libraries including the decay constants, yield
matrix and one-group cross sections have been used and greatly simplified for a calculation
efficiency. The computational results for the benchmark problems including the UO2 and MOX
fuels show that the depletion module of the whole-core transport code DeCART works
reasonably, well.
