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  • Abnormal_Grain_Growth_Fuel_Clad_25_11_2020_OA

    Rights statement: This is the author’s version of a work that was accepted for publication in Journal of Nuclear Materials Changes resulting from the publishing process, such as peer review, editing, corrections, structural formatting, and other quality control mechanisms may not be reflected in this document. Changes may have been made to this work since it was submitted for publication. A definitive version was subsequently published in Journal of Nuclear Materials, 543, 2021 DOI: 10.1016/j.jnucmat.2020.152633

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Grain Secondary Recrystallisation in Advanced Gas Cooled Reactor Fuel Cladding: Characterisation and Modelling

Research output: Contribution to journalJournal articlepeer-review

Published
Article number152633
<mark>Journal publication date</mark>1/01/2021
<mark>Journal</mark>Journal of Nuclear Materials
Volume543
Number of pages14
Publication StatusPublished
Early online date28/10/20
<mark>Original language</mark>English

Abstract

Secondary recrystallisation and resultant abnormal grain growth behaviour in a specific nano-particle pinned stainless steel alloy have been investigated under a particular combination of stress and annealing conditions. The tests were carried out as function of time and temperature in order to study the effect of specific grain size distributions and grain growth models. The models of size distribution and grain growth were first revisited and applied to estimate the incubation time for the explored temperatures. The pre-required sample history is pointed out as an important issue. The grain particle size data are obtained for samples of known prior cold work and recrystallisation conditions. Careful application of the grain growth model shows that the analysis of the mean sizes of the grains and the nano-particles should be more precise and accurate than currently measured to achieve a correct evaluation of incubation time. Recommendations on additional R&D work on the way to apply the model and to avoid secondary grain growth are consequently suggested.

Bibliographic note

This is the author’s version of a work that was accepted for publication in Journal of Nuclear Materials Changes resulting from the publishing process, such as peer review, editing, corrections, structural formatting, and other quality control mechanisms may not be reflected in this document. Changes may have been made to this work since it was submitted for publication. A definitive version was subsequently published in Journal of Nuclear Materials, 543, 2021 DOI: 10.1016/j.jnucmat.2020.152633