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Calculations Simulating Spent-Fuel Leaching Experiments

Hilbert Christensen

Nuclear Technology / Volume 124 / Number 2 / November 1998 / Pages 165-174

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT98-A2916

Calculations of UO2-fuel corrosion and gas production from radiolysis of water have been carried out. The calculations simulated conditions of spent-fuel leaching experiments carried out within a European Union project. In some of these experiments, carried out by Forschungszentrum Karlsruhe, a fuel pellet was exposed in deionized water for 200 days, and fuel alteration and gas production rates were measured. A radiolysis model, developed previously, was used to calculate the oxidation of UO2 caused by water radiolysis products. The calculated fuel alteration rate was 2.2 × 10-8 mol UO2(g U)-1day-1, about three times higher than the experimental rate, 6.3 × 10-9 mol UO2(g U)-1day-1.

The fair agreement between calculated and experimental corrosion rates shows that the model may be used for prediction of corrosion behavior of spent fuel in the repository. The calculated gas generation rates were 2 × 10-8 and 1 × 10-8 mol(g U)-1day-1 for hydrogen and oxygen, respectively, about six times lower than the experimental values.