Verification of Microscopic Depletion Module of Diffusion Code RAST-K 2.0

In the nuclear design procedure, especially two step method many diffusion code such as RAST-K 1.0, SIMULATE, PARCS adopt macroscopic depletion. Also MASTER use few heavy nuclide chain and it leads to huge number density error in the initial burnup step points. Basically, macroscopic depletion of diffusion code use macroscopic cross section from the result of depletion calculation of transport code. But transport code assume that a single fuel assembly is infinitely arranged, so it leads to inconsistent macroscopic cross section generation using different neutron spectrum due to different situation with diffusion code where different fuel assemblies which has different burnup and enrichment are arranged. In addition, there are inconsistent macroscopic cross section by interpolating burnup due to difference between burnup point of transport code and burnup point of diffusion code. Microscopic depletion module has been implemented in diffusion code RAST-K 2.0 and its accuracy has been compared with MASTER