DEVELOPMENT OF A MODELING APPROACH TO ESTIMATE RADIATION FROM A SPENT FUEL ROD QUIVER

Before encapsulation of spent nuclear fuel in a geological repository, the fuels need to be verified for safeguards purposes. This requirement applies all assemblies, including those with properties or designs that are especially challenging verify. One such example quivers, new type containers used hold damaged rods. After placing rods inside they sealed thick lid and water is removed. The enough significantly reduce amount gamma radiation penetrating through it, which can make verification from top using techniques difficult. Considering number quivers at storage facilities foreseen increase near future, studying feasibility timely. In this paper we study related aimed investigating neutron field around quiver designed by Westinghouse AB filled PWR irradiated Swedish Ringhals site. A simplified geometry detailed operational history each rod provided reactor operator, respectively. nuclide inventory placed emission source terms calculated ORIGEN-ARP. transport modeled Serpent2 Monte Carlo code. first objective assess capability attribute tester (SFAT) verify content results show attenuates radiation, thereby making based above