Performance evaluation of accident tolerant Cr-coated Zr alloy cladding under accident conditions based on a refined degradation model-Reference-Cited by-同舟云学术

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Performance evaluation of accident tolerant Cr-coated Zr alloy cladding under accident conditions based on a refined degradation model

Published:2024-11 Issue: Volume:176 Page:105359
ISSN:0149-1970
Container-title:Progress in Nuclear Energy
language:en
Short-container-title:Progress in Nuclear Energy

Author:

Wu Shihao,Wang Dong,Zhang Yapei,Wu Xiaocheng,Tian Wenxi,Qiu Suizheng,Su G.H.

Funder

National Natural Science Foundation of China

Publisher

Elsevier BV

Reference37 articles.

1. A study on the feasibility of using Uranium Nitride (UN) fuel in Pressurized water reactors (PWR);Aziz;Ales. Eng. J.,2023

2. Effect of chromium coated zircaloy cladding of accident tolerant fuel on the best estimate LOCA methodology;Bae;Prog. Nucl. Energy,2022

3. High temperature steam oxidation of chromium-coated zirconium-based alloys: kinetics and process;Brachet;Corrosion Sci.,2020

4. Microstructure and high-temperature steam oxidation properties of thick Cr coatings prepared by magnetron sputtering for accident tolerant fuel claddings: the role of bias in the deposition process;Chen;Corrosion Sci.,2020

5. Finite element based fuel performance investigation of U3Si2–FeCrAl design under normal and RIA conditions;Deng;Prog. Nucl. Energy,2022

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