| abstract |
A flux trap neutron absorber arrangement for use in a fuel storage body between a pair of fuel storage cans which receive and store nuclear fuel assemblies includes separate pockets spaced from one another and extending vertically along and attached to the exterior of each of the adjacent side walls of adjacent spaced storage cans, an elongated flat plate of a thermal neutron absorber material mounted in each pocket, the plates of thermal neutron absorber material being likewise spaced from one another and defining a fast neutron slow-down region therebetween, a slab of a metal hydride disposed in the fast neutron slow-down region between the plates of thermal neutron absorber material and the separate pockets on the adjacent side walls, a canister containing the slab of the metal hydride being disposed in the fast neutron slow-down region, the canister being connected to at least one of the adjacent side walls of the adjacent storage cans. The thermal neutron absorber material of the plates is usually boron carbide. Preferably, the metal hydride of the slabs is usually titanium hydride. |