Chromium-coated cladding analysis under simulated LOCA burst conditions
Author:
Funder
Department of Energy
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference23 articles.
1. Cathcart, J., et al. Zirconium metal-water oxidation kinetics. IV. Reaction rate studies. 1977. Oak Ridge National Lab.
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4. Accident tolerant fuel cladding development: Promise, status, and challenges;Terrani;Journal of Nuclear Materials,2018
5. Early studies on Cr-Coated Zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water reactors;Brachet;Journal of Nuclear Materials,2019
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1. Source term analysis of FeCrAl accident tolerant fuel using MELCOR;Annals of Nuclear Energy;2024-07
2. Fuel performance analysis of Cr-coated Zircaloy-4 cladding during a prototypical LOCA event using BISON;Annals of Nuclear Energy;2024-06
3. Elucidating changes in thermal creep strain rate of Cr-coated Zr-Nb alloy Accident Tolerant Fuel (ATF) cladding via experiment and mechanical analysis;Journal of Nuclear Materials;2024-04
4. Fuel Performance Modelling of Cr-Coated Zircaloy Cladding Under Dba/Loca Conditions;2024
5. High temperature creep model development using in-situ 3-D DIC techniques during a simulated LOCA transient;Annals of Nuclear Energy;2023-12
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