Author:
Ilham Muhammad,Raflis Helen,Suud Zaki
Abstract
Abstract
This paper discusses the development of program code that coupling the ORIGEN2.2 for burn-up analysis with the Monte Carlo program OpenMC for neutron analysis program called OpenMC-ORIGEN (Op-OR). The results of the program have been compared with benchmark results from previously published results and MCNP6 program. The acquired results show a good agreement with benchmark results. This linkage program codes performed well for designing a new advanced reactor and analysing the neutronics parameter and burnup/depletion calculation.
Subject
General Physics and Astronomy