Abstract:
With cooperation of the International Atomic Energy Agency (IAEA) and the Department of Energy (DOE) of the United States, several calculations and tasks related to the waste disposal of spent MTR-HEU fuel enriched nominally to 93% were carried out for the conversion of the IAN-R1 Research Reactor from MTRHEU fuel to TRIGA-LEU fuel. In order to remove the spent MTR-HEU fuel of the core and store it safely a project was established at the Instituto de Ciencias Nucleares y Energìas Alternativas (INEA). This project included training, acquisition of hardware and software, design and construction of a decay pool, transfer of the spent HEU fuel elements into the decay pool and his final transport in 1996 to Savannah River Site in United States. In this paper are presented neutronic and shielding calculations for the decay pool concerning the storage of spent MTR-HEU fuel elements.