Gamma and neutron source term calculation for irradiated TRIGA Mark II fuel using ORIGEN2

Abstract

TRIGA Mark II has served as nuclear research reactor for decades, which is to provide research facility towards nuclear development as well as for trainings in the aspect of education and industry. Standard TRIGA fuel, UZrH1.6 is used in this reactor which can be found in two types; aluminium or stainless steel cladding. In this study, stainless steel cladded fuel used in Reactor TRIGA PUSPATI (RTP) that consists of fissile U-235 with 19.9% enrichment and 20% weight of Uranium is used as reference for input data. The irradiated fuel inventories and fuel burnup were determined using ORIGEN2 code by referring to PWR data library, consists of gamma and neutron source term comes from activation products, actinides and fission products after 18 years of irradiation and 5 years of cooling period with 200 days of time step. The outcomes from this study can be concluded with the inventories from fission products to be the highest in all categories, in which the U-235 depleted up to 52.9%. The results from this simulation is crucial as it is then carried forward for radiation shielding for interim storage facility.