Predictions of dry storage behavior of zircaloy clad spent fuel rods using deformation and fracture map analyses

Predictions of the maximum initial allowable temperature required to a 40-year life in dry storage are made for Zircaloy clad spent fuel. Maximum initial dry storage temperatures of 4200C for 1 year fuel cladding subjected to a constant stress of 70 MPa are predicted. The technique utilized in this work is based on the deformation and fracture map methodology. Maps are presented for temperatures between 50 and 8500C and stresses between 5 and 500 MPa. These maps are combined with a life fraction rule to predict the time to rupture of Zircaloy clad spent Light Water Reactor (LWR) fuel subjected to various storage conditions