Validation of COREBN/HIST computer code for RSG-GAS core fuel management and burn-up calculation

To ensure that the computer code can be used and applied to RSG-GAS core nuclear parameter calculation, for example SRAC code, it is need to validate the code. SRAC computer code is consists of 5 calculation modules, those are PIJ, ANISN, TWOTRAN, TUD and CITATION, and also 2 option burn-up calculation modules ASMBURN and COREBN/HIST. In this study, the validation was performed to COREBN/HIST module of SRAC COREBN/HIST is a module used for fuel burn-up calculation and for multi dimensional core fuel management. The fuel burn-up calculation based on solving differential diffusion equation using finite different method and insertion of prepared macroscopic cross-section. Calculation of burn-up distribution and reactivity has been done for the first and 45^th RSG-GAS cores. The calculation result showed that the excess reactivity at BOC using COREBN has no significant difference compared to experiment data and 2 dimensional calculation result using ASMBURN. The changing in fuel burn-up fraction of 45^th core for one cycle length, showed that there is no significant diverse value between calculation using COREBN and ASMBURN at the position closed to beryllium block reflector. There is also no significant difference in percentage of heavy nuclide inventory contained in the discharge burn-up fuel for the two modules of the SRAC Therefore, module COREBN/HIST of SRAC computer code for the fuel burn-up calculation and fuel management of RSG-GAS core is be able run. (author)