Short Communication: Observation of Initial Burst Release of Fission Gas from High-Burnup UO2 Nuclear Fuel During Thermal Transient
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference12 articles.
1. Fission gas release from UO2 nuclear fuel: A review;Rest;Journal of Nuclear Materials,2019
2. On the condition of UO2 nuclear fuel irradiated in a PWR to a burn-up in excess of 110 MWd/kgHM;Restani;Journal of Nuclear Materials,2016
3. EPMA and SEM of fuel samples from PWR rods with an average burn-up of around 100 MWd/kgHM;Manzel;Journal of Nuclear Materials,2002
4. High burnup changes in UO2 fuels irradiated up to 83 GWd/t in M5® claddings;Noirot;NUCLEAR ENGINEERING AND TECHNOLOGY,2009
5. An Assessment of the Fuel Pulverization Threshold During LOCA-Type Temperature Transients;Turnbull;Nuclear Science and Engineering,2015
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1. Transient behavior of oxide fuels with controlled microstructure and Cr2O3 additive;npj Materials Degradation;2024-07-16
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