Uncertainty analysis of ATF Cr-coated-Zircaloy on BWR in-vessel accident progression during a station blackout-Reference-Cited by-同舟云学术

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Uncertainty analysis of ATF Cr-coated-Zircaloy on BWR in-vessel accident progression during a station blackout

Published:2021-09 Issue: Volume:213 Page:107770
ISSN:0951-8320
Container-title:Reliability Engineering & System Safety
language:en
Short-container-title:Reliability Engineering & System Safety

Author:

Guo Zehua,Dailey Ryan,Feng Tangtao,Zhou Yukun,Sun Zhongning,Corradini Michael L,Wang Jun

Funder

Massachusetts Institute of Technology

US Department of Energy

Publisher

Elsevier BV

Subject

Industrial and Manufacturing Engineering,Safety, Risk, Reliability and Quality

Reference46 articles.

1. Current status of materials development of nuclear fuel cladding tubes for light water reactors;Duan;Nucl Eng Des,2017

2. Out-of-pile performance of surface-modified Zr cladding for accident tolerant fuel in LWRs;Kim;J Nucl Mater,2018

3. Accident tolerant fuels for LWRs: a perspective;Zinkle;J Nucl Mater,2014

4. Protective coatings on zirconium-based alloys as accident-tolerant fuel (ATF) claddings;Tang;Corros Rev,2017

5. Development status of accident-tolerant fuel for light water reactors in Korea;Kim;Nucl Eng Technol,2016

Cited by 37 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Comparative study on high-temperature air and steam oxidation of Cr-coated Zr-4 alloy through experimental and DFT calculation;Journal of Nuclear Materials;2025-01

2. Performance evaluation of accident tolerant Cr-coated Zr alloy cladding under accident conditions based on a refined degradation model;Progress in Nuclear Energy;2024-11

3. Exploring the effect of Si content in Cr coating on its microstructure and properties;Surface and Coatings Technology;2024-10

4. Source term analysis of FeCrAl accident tolerant fuel using MELCOR;Annals of Nuclear Energy;2024-07

5. Numerical simulation prediction of critical heat flux for 5 × 5 rod bundle with multiple grid spacers and different cladding materials;Annals of Nuclear Energy;2024-06

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