Post-LOCA ductility of Cr-coated cladding and its embrittlement limit
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference26 articles.
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3. High-temperature oxidation behavior and degradation mechanism of chromium-coated zirconium alloy cladding: a review;Tungsten;2024-09-05
4. Research progress on the preparation of irradiation-resistant coating based on PVD technology;Journal of Materials Research and Technology;2024-09
5. 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
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