Fission Gas Release from UO2+xin Defective Fuel Rods
Author:
Affiliation:
1. Argonne National Laboratory Engineering Division, P.O. Box 2528, Idaho Falls, Idaho 83403
Publisher
Informa UK Limited
Subject
Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.13182/NT00-A3073
Reference21 articles.
1. Fuel oxidation and irradiation behaviors of defective BWR fuel rods
2. Steam oxidation of fuel in defective LWR rods
3. Measurements of the thermal conductivity of uranium dioxide at 670–1270 k
4. Self-diffusion of uranium in UO2
5. The response of fission gas bubbles to the dynamic behavior of point defects
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2. Towards modelling defective fuel rods in TRANSURANUS: Benchmark and assessment of gaseous and volatile radioactive fission product release;Annals of Nuclear Energy;2024-03
3. Experimental investigation of Kr diffusion in UO2+: Slight deviations from stoichiometry, significant effects on diffusion kinetics and mechanisms;Journal of Nuclear Materials;2023-02
4. Grain-scale study of the grain boundary effect on UO2 fuel oxidation and fission gas release under reactor conditions;Chemical Engineering Science;2021-01
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