PREDICTION OF RTP FUEL SOURCE TERM AND DECAY HEAT IN SURROUNDING MATERIALS

Abstract

This study aims to predict the source term and decay heat of highly burned-up fuel from the RTP TRIGA reactor, a critical factor for ensuring safe handling and disposal. Data on the reactor's operational history and accumulated burnup were collected and analyzed. Burnup calculations were carried out using the TRIGLAV code, while nuclide inventory simulations were performed with the MCNPX code. The decay heat was also evaluated using MCNPX. The gamma radiation strength for a core case and the decay heat resulting from energy deposition within the spent fuel pool were assessed. Additionally, the conservative maximum source term for a single fuel element was determined, highlighting the contribution of gamma radiation from radionuclides to decay heat in surrounding materials. This study provides vital data on the source term and decay heat, supporting the safe management of spent fuel from the TRIGA reactor.