A hybrid simulation methodology for modeling dynamic recrystallization in UO2 LWR nuclear fuels
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference48 articles.
1. M.L. Blieberg, R.M. Berman, B. Lustman, Effects of high burn-up on oxide ceramic fuels, in: IAEA, Radiation Damage in Solids and Reactor Materials, Vienna, 1963, p. 319.
2. Oxide fuel transients
3. High magnification SEM observations for two types of granularity in a high burnup PWR fuel rim
4. Rim structure formation of isothermally irradiated UO2 fuel discs
5. On the thermal conductivity of UO2 nuclear fuel at a high burn-up of around 100MWd/kgHM
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