Out-reactor nodular corrosion behaviour of zircaloys-Reference-Cited by-同舟云学术

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Out-reactor nodular corrosion behaviour of zircaloys

Published:1983-12 Issue:2-3 Volume:119 Page:208-218
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Ramasubramanian N.

Publisher

Elsevier BV

Subject

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

Reference12 articles.

1. Zirconium in the Nuclear Industry;Trowse,1977

2. Zirconium in the Nuclear Industry;Sheppard,1977

3. Zirconium in the Nuclear Industry;Johnson,1977

4. A preliminary correlation between the accelerated corrosion of zircaloy in BWR's and in high temperature, high pressure steam

Cited by 14 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. Microstructural understanding of general and localized corrosion of Fe13Cr4Al2Mo1.2Nb alloy in high temperature aerated water and superheated steam;Corrosion Science;2022-07

2. Localized oxidation of Zr-2.5Nb alloy in high temperature carbon dioxide environment containing hydrochloric acid;Corrosion Science;2020-02

3. Nodular Corrosion of Zr–0.85Sn–0.16Nb–0.37Fe–0.18Cr Alloy in 500 °C Steam Caused by High-temperature Processing;Oxidation of Metals;2019-10-10

4. The oxidation behaviour of Ce-5 at.% La in air at ambient temperature;Solid State Ionics;2017-12

5. A novel mechanism for nodular corrosion of Zircaloy-4 corroded in 773 K superheated steam;Corrosion Science;2017-09

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