[HTML][HTML] Spent nuclear fuel in dry storage conditions–current trends in fuel performance modeling

P Konarski, C Cozzo, G Khvostov… - Journal of Nuclear …, 2021 - Elsevier
The role of dry storage in spent nuclear fuel management becomes more and more
important. Originally intended to serve as a temporary solution for a few decades until final …

Investigation of δ zirconium hydride morphology in a single crystal using quantitative phase field simulations supported by experiments

PCA Simon, LK Aagesen, AM Jokisaari… - Journal of Nuclear …, 2021 - Elsevier
In light water nuclear reactors, waterside corrosion of the cladding material leads to the
production of hydrogen, a fraction of which is picked up by the zirconium cladding and …

Predicting the hydride rim by improving the solubility limits in the Hydride Nucleation-Growth-Dissolution (HNGD) model

F Passelaigue, PCA Simon, AT Motta - Journal of Nuclear Materials, 2022 - Elsevier
During operation of a light water reactor, waterside corrosion of the Zircaloy nuclear fuel
cladding causes hydrogen pickup. The absorbed hydrogen can redistribute in the cladding …

Simulation of hydrogen diffusion along the axial direction in zirconium cladding tube during dry storage

C Lee, Y Lee - Journal of Nuclear Materials, 2023 - Elsevier
This study presents an updated mHNGD (modified hydrogen nucleation-growth-dissolution)
model by improving atomic fraction of solid solution hydrogen with the use of instantaneous …

Determination of the hydrogen heat of transport in Zircaloy-4

S Kang, PH Huang, V Petrov, A Manera, T Ahn… - Journal of Nuclear …, 2023 - Elsevier
During operation in a nuclear reactor, Zr-based nuclear fuel cladding is subject to waterside
corrosion which can lead to hydrogen ingress. The hydrogen that enters the material will …

Hydride reorientation and its impact on mechanical properties of high burn-up and unirradiated cold-worked stress-relieved Zircaloy-4 and ZirloTM fuel cladding

Q Auzoux, P Bouffioux, A Machiels, S Yagnik… - Journal of Nuclear …, 2022 - Elsevier
Precipitation of radial hydrides in zirconium-based cladding concomitant with the cooling of
spent nuclear fuel can potentially compromise cladding integrity during its subsequent …

The Effect of Long Isothermal Holds on Hydride Dissolution and Precipitation Behavior in Zircaloy-2 and Zr-2.5 Nb

SM Hanlon, T Skippon, I Muir… - Zirconium in the …, 2023 - asmedigitalcollection.asme.org
Absorbed hydrogen impacts the structural integrity of zirconium alloy components,
particularly under conditions in which hydrides form. Improving the understanding of …

Modeling hydrogen localization in Zircaloy cladding subjected to temperature gradients

KRB Nantes, M Jin, AT Motta - Journal of Nuclear Materials, 2024 - Elsevier
In light water reactors, Zr-based alloys used for nuclear fuel cladding undergo oxidation and
absorb hydrogen, which can precipitate as brittle zirconium hydrides. During reactor normal …

Modeling hydride growth and strain-field evolution at a stress concentrator in zirconium alloys

S Aiyeru, P Saidi, MR Daymond - Computational Materials Science, 2023 - Elsevier
The redistribution of hydrogen in zirconium-based components of nuclear reactors is
strongly influenced by local stress states. Such a stress-state can be influenced by the stress …

Finite element modeling of hydrogen migration and hydride precipitation in Zr alloys

S Aiyeru, P Saidi, MR Daymond - Computational Materials Science, 2023 - Elsevier
Abstract The Finite Element software, ABAQUS® together with subroutine codes written in
FORTRAN is used to fully couple the mass diffusion–displacement analysis of hydrogen …