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Systematic approach to predicting corrosion of zirconium alloys in the water coolant of nuclear reactors

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Atomic Energy Aims and scope

A method of semiempirical prediction of corrosion of cladding zirconium alloys as a function of the operating conditions and composition is presented. The laws of thermodynamics and chemical kinetics of the oxidation reactions of a multicomponent zirconium alloy form the physicochemical basis of the computational method. The method is based on a model developed at the All-Russia Research and Design Institute of Integrated Power Technology for the corrosion of commercial and experimental zirconium alloys in water media under autoclave and reactor conditions taking account of the composition of the alloy and the water chemistry. The model is verified on the basis of independent tests performed on a series of zirconium alloys under autoclave and reactor conditions. The method developed makes it possible to predict the corrosion of fuel-element cladding made from zirconium alloys with fuel burnup to 80 MW·days/kg under the conditions of one- and two-phase VVER and RBMK coolant.

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  1. All-Russia Research and Design Institute of Integrated Power Technology (VNIPIET), St. Petersburg, Russia

    V. G. Kritskii & I. G. Berezina

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  1. V. G. Kritskii
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  2. I. G. Berezina
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Translated from Atomnaya Énergiya, Vol. 110, No. 4, pp. 219–227, April, 2011.

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Kritskii, V.G., Berezina, I.G. Systematic approach to predicting corrosion of zirconium alloys in the water coolant of nuclear reactors. At Energy 110, 265–276 (2011). https://doi.org/10.1007/s10512-011-9421-5

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