INVESTIGATION OF WWER-1OOO SPENT FUEL BEHAVIOUR UNDER DRY STORAGE CONDITIONS

Year
1996
Author(s)
I.M. Kadarmetov - A.A.Bochvar All-Russia Research Institute of Inorganic Materials
Yu.K. Bibilashvili - A.A.Bochvar All-Russia Research Institute of Inorganic Materials
Abstract
In the work presented prominence is given to the problem of fiel cladding integrity during dry storage in an inert gas, as a primary barrier between the environment and radioactive fission products. Post-irradiation thermal creep of Zr-l%Nb cladding is studied experimentally. A method is suggested to determine the time of safe long-term storage of spent WWER-1OOOfuel that takes into account the pre-histoxy of fuel assembly irradiation and cooling in water pools. Preliminmy assessments of the maximum allowable temperatures of the WWER-1OOOspent fuel dry storage in inert gases are made.