Controlling low temperature sintering of UO2+x-Reference-Cited by-同舟云学术

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Controlling low temperature sintering of UO2+x

Published:2024-11 Issue: Volume:600 Page:155269
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Frost Dillon G.,Burr Patrick A.,Obbard Edward G.,Veliscek-Carolan Jessica^ORCID

Publisher

Elsevier BV

Reference40 articles.

1. Review of sintering and densification in nuclear fuels: physical mechanisms, experimental results, and computational models;Greenquist;J. Nucl. Mater.,2018

2. Rim structure formation and high burnup fuel behavior of large-grained UO2 fuels;Une;J. Nucl. Mater.,2000

3. Effect of grain size on microstructural change and damage recovery in UO2 fuels irradiated to 23 GWd/t;Nogita;J. Nucl. Sci. Technol.,1994

4. The effect of additives on the irradiation behaviour of UO2;Killeen;J. Nucl. Mater.,1975

5. Effect of initial grain size on fission gas release from irradiated UO2 fuel;Hastings;J. Am. Ceram. Soc.,1983

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