On the relationship between dynamic solubility, multi-atom bubble nucleation, irradiationinduced re-solution, and the bubble size distribution in Xe implanted Mo
Date
2013
Authors
Rest, D.
Yun, B. Ye
Insepov, Z.
Journal Title
Journal ISSN
Volume Title
Publisher
Argonne National Laboratory
Abstract
U-Mo alloys are candidate fuels for both research and test reactors, as well as for advanced power reactors. A critical requirement for these candidate fuels is stable swelling behavior over their expected lifetime. In-reactor deformation of these materials is primarily driven by irradiation induced swelling where the primary component is fission gas (Xe and Kr) generated by decay of the primary fission products.
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Citation
"J. Rest, D. Yun, B. Ye, and Z. Insepov. On the relationship between dynamic solubility, multi-atom bubble nucleation, irradiationinduced re-solution, and the bubble size distribution in Xe implanted Mo. Argonne National Laboratory. Transactions of the American Nuclear Society, 2013, 108:353-356"