High-temperature oxidation of thick Cr coating prepared by arc deposition for accident tolerant fuel claddings-Reference-Cited by-同舟云学术

High-temperature oxidation of thick Cr coating prepared by arc deposition for accident tolerant fuel claddings

Published:2019-06 Issue: Volume:519 Page:145-156
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Hu Xiaogang^ORCID,Dong Chuang^ORCID,Wang Qing,Chen Baoqing,Yang Hongyan,Wei Tianguo,Zhang Ruiqian,Gu Wei,Chen Damin

Funder

National key research and development program of China

National Natural Science Foundation of China

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference23 articles.

1. Assessment at CEA of coated nuclear fuel cladding for LWRs with increasing margins in LOCA and beyond LOCA conditions;Idarraga-Trujillo,2013

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

3. Fabrication of SiC–SiC composites for fuel cladding in advanced reactor designs;Deck;Prog. Nucl. Energy,2012

4. Accident Tolerant FeCrAl Fuel Cladding: Current Status towards Commercialization;Field,2017

5. CEA Studies on Advanced Nuclear Fuel Claddings for Enhanced Accident Tolerant LWRs Fuel (LOCA and beyond LOCA Conditions), Fontevraud 8-Contribution of Materials Investigations and Operating Experience to LWRs' Safety;Brachet,2015

Cited by 94 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. Effect of Mo interlayer on the diffusion behavior and mechanical property of Cr-coated Zr alloy cladding tubes;Materials Today Communications;2024-12

3. Microstructure evolution and degradation mechanisms of amorphous FeCrAlMoSiY coated Zr in 1200 °C steam;Vacuum;2024-11

4. Microstructural characteristics of multilayers and interfaces of Cr-coated Zircaloy-4 cladding based on elemental diffusion under high-temperature steam oxidation;Journal of Nuclear Materials;2024-10

5. High-temperature oxidation behavior and degradation mechanism of chromium-coated zirconium alloy cladding: a review;Tungsten;2024-09-05