A MODEL FOR RADIATION CORROSION OF ZIRCONIUM CLADDING OF FUEL-ELEMENTS IN BOILING WATER NUCLEAR-REACTORS .1. UNIFORM CORROSION

A model is worked out to describe the depth of uniform corrosion of zi rconium fuel-element claddings under conditions of boiling water nucle ar reactors in terms of measurable parameters that characterize the op eration of the nuclear reactor (the flux of fast neutrons, temperature and the steam content of the coolant, etc.). The model is based on th e radiolytic corrosion mechanism, namely, on relating the rate of clad ding corrosion to H2O2 concentration in the coolant. Approximate expre ssions useful for the primary treatment and comparison of the results of corrosion tests are presented.