Effects of Cr/Zircaloy-4 coating qualities for enhanced accident tolerant fuel cladding
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference50 articles.
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3. Burst and oxidation behavior of Cr-coated Zirlo during simulated LOCA testing;Bell;J. Nucl. Mater.,2022
4. M. Billone, Y. Yan, T. Burtseva, R. Daum, Cladding Embrittlement During Postulated Loss-of-Coolant Accidents (NUREG/CR-6967), 2008. https://www.nrc.gov/reading-rm/doc-collections/nuregs/contract/cr6967/index.html (accessed January 31, 2023).
5. AREVA NP’s enhanced accident-tolerant fuel developments: Focus on Cr-coated M5 cladding;Bischoff;Nucl. Eng. Technol.,2018
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1. Dispersal of high-burnup fuel fragment surrogate particles during and after loss-of-coolant accident tests;Nuclear Engineering and Design;2024-08
2. Fuel Performance Modelling of Cr-Coated Zircaloy Cladding Under Dba/Loca Conditions;2024
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