Chemical interactions between ZrO2/α-Zr structured Zircaloy-4 and 316 stainless steel-B4C melt at 1300 °C-Reference-Cited by-同舟云学术

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Chemical interactions between ZrO2/α-Zr structured Zircaloy-4 and 316 stainless steel-B4C melt at 1300 °C

Published:2022-02 Issue: Volume:559 Page:153416
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Zheng Lichun,Wang Feiyu,Li Huabing,Jiang Zhouhua,Ueda Shigeru

Funder

Fundamental Research Funds for the Central Universities

National Natural Science Foundation of China

China Postdoctoral Science Foundation

Publisher

Elsevier BV

Subject

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

Reference33 articles.

1. The effect of post-irradiation annealing on the stress corrosion crack growth rate of neutron-irradiated 304 L stainless steel in boiling water reactor environment;Kuang;Corros. Sci.,2019

2. Effect of beta-to-alpha phase transition rate on corrosion behaviour of Zircaloy;Massih;Corros. Sci.,2006

3. Oxidation behaviour of Zr-1.7Sn-2.3Hf alloy in nitrogen-containing steam at 1200 °C;Zheng;Corros. Sci.,2018

4. Enrichment of Fe and Ni at metal and oxide grain boundaries in corroded Zircaloy-2;Sundell;Corros. Sci.,2012

5. The kinetics of oxidation of Zircaloy-4 in steam at high temperatures;Pawel;J. Electrochem. Soc.,1979

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