Study on eutectic-oxidation coupling reaction of Cr-Zr system in high temperature steam environment-Reference-Cited by-同舟云学术

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Study on eutectic-oxidation coupling reaction of Cr-Zr system in high temperature steam environment

Published:2024-08 Issue: Volume:596 Page:155082
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Wang Dong,Zhong Ruhao,Wu Xiaocheng,Zhang Yapei,Li Xiurui,Yu Jian,Lan Yicong,Su G.H.,Qiu Suizheng,Tian Wenxi,Liao Yehong,Peng Zhenxun,Guo Chao,Song Zhongxiao,Sun Jun

Funder

National Natural Science Foundation of China

Publisher

Elsevier BV

Reference50 articles.

1. Insights from review and analysis of the Fukushima Dai-ichi accident;Hirano;J. Nucl. Sci. Technol.,2012

2. A review on analysis of LWR severe accident;Zhang;J. Nucl. Eng. Radiat. Sci.,2015

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

4. Accident tolerant fuel cladding development: promise, status, and challenges;Terrani;J. Nucl. Mater.,2018

5. Alloy design and characterization of a recrystallized FeCrAl-ODS cladding for accident-tolerant BWR fuels: an overview of research activity in Japan;Ukai;J. Nucl. Mater.,2023

Cited by 1 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. Early-stage diffusion and oxidation behavior of Cr-Nb coated Zr alloy accident tolerant fuel cladding materials at 1200°C–1500°C;Journal of Nuclear Materials;2024-10

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