Hydrogen redistribution in Zr-base cladding under gradients in temperature and stress

Abstract

Computational models are used here for simulating diffusion-controlled redistribution of hydrogen that is picked up by zirconium-base nuclear fuel cladding during light water reactor operation. Axial localization of hydrogen, leading to localized precipitation of zirconium hydrides at lower-temperature regions near interpellet gaps, is studied with a bespoke model, while radial diffusion, leading to formation of a densely hydrided rim subjacent to the waterside oxide layer, is studied with a more general model. The calculated results are compared with experimental observations and similar computational studies reported in the literature. The results underline the importance of hydrogen redistribution with regard to local embrittlement of the cladding tubes.