Recent Developments of Zirconium Alloys in the Nuclear Industry

A special issue of Metals (ISSN 2075-4701). This special issue belongs to the section "Metallic Functional Materials".

Deadline for manuscript submissions: 30 November 2024 | Viewed by 53

Special Issue Editor


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Guest Editor
State Key Laboratory for Advanced Metals and Materials, University of Science and Technology Beijing, Beijing 100083, China
Interests: zirconium alloy
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Special Issue Information

Dear Colleagues,

With the development of the nuclear power industry, the number of nuclear power plants has had a rapid increase globally, especially in China. Zirconium alloy, as one of the best cladding materials, is receiving more and more attention. Research on the new alloy development and mechanical behavior, hydrogen pick-up and hydrides, in-reactor behavior and irradiation effects, corrosion, accident tolerance design, etc., of zirconium alloys has achieved significant progress. In order to better understand the current issues and predict the future development of zirconium alloys, it is necessary to summarize research for discussion. This Special Issue aims at this purpose and wishes to play a positive role in promoting the development of zirconium alloys in nuclear power.

Prof. Dr. Xiping Song
Guest Editor

Manuscript Submission Information

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Keywords

  • zirconium alloy
  • mechanisms of corrosion
  • processing and mechanical properties
  • irradiation effects on corrosion
  • in-reactor behavior
  • high-temperature transients
  • hydrogen effects

Published Papers

This special issue is now open for submission.
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