Thermodynamic considerations and prediction of the primary coolant activity of 99Tc

Abstract A physical model has been developed to describe the coolant activity behaviour of 99 Tc, during constant and reactor shutdown operations. This analysis accounts for the fission production of technetium and molybdenum, in which their chemical form and volatility is determined by a thermodynamic treatment using Gibbs-energy minimization. The release kinetics are calculated according to the rate-controlling step of diffusional transport in the fuel matrix and vaporization from the fuel-grain surface. Based on several in-reactor tests with defective fuel elements, and as supported by the thermodynamic analysis, the model accounts for the washout of molybdenum from the defective fuel on reactor shutdown. The model also considers the recoil release of both 99 Mo and 99 Tc from uranium contamination, as well as a corrosion source due to activation of 98 Mo. The model has provided an estimate of the activity ratio 99 Tc/ 137 Cs in the ion-exchange columns of the Darlington Nuclear Generating Station, i.e., 6 × 10 −6 (following ∼200 days of steady reactor operation) and 4 × 10 −6 (with reactor shutdown). These results are consistent with that measured by the Battelle Pacific Northwest Laboratories with a mixed-bed resin-sampling device installed in a number of Pressurized Water Reactor and Boiling Water Reactor plants.