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Metals
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Radiation Damage and Irradiation-Assisted Stress Corrosion Cracking of Metallic Materials...
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Radiation Damage and Irradiation-Assisted Stress Corrosion Cracking of Metallic Materials for Reactor Applications

A special issue of Metals (ISSN 2075-4701). This special issue belongs to the section "Metal Failure Analysis".

Deadline for manuscript submissions: closed (30 March 2022) | Viewed by 1579

Special Issue Editor

Prof. Dr. Miao Song

E-Mail Website
Guest Editor
School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai, 200240, China
Interests: nuclear materials and structural materials; radiation effects; irradiation-assisted stress corrosion cracking; additive manufacturing for nuclear applications

Special Issue Information

Dear Colleagues,

Most light water reactors (LWRs) of the existing fleet worldwide are expected to continue operation beyond their original operating license for 60–80 years. The reliability of structural materials for core internals is a critical and potentially life-limiting event for LWRs. Irradiation-assisted stress corrosion cracking (IASCC) is the primary degradation mechanism for stainless steel (SS) core internals. However, the detailed underlying mechanisms of IASCC is yet to be elucidated. The purpose of this Special Issue on “Radiation Damage and Irradiation-Assisted Stress Corrosion Cracking of Metallic Materials for Reactor Applications” is to explore the radiation damage and radiation effects or the potential factors that influenced irradiation-assisted stress corrosion cracking in nuclear power systems.

This Speical Issue will cover but not be limited to experimental or simulation efforts (both original research or review articles) that advance our understandings in radiation damage, radiation-induced segregation, radiation-induced/enhanced precipitations, irradiation accelerated/decelerated corrosion, stress corrosion cracking, irradiation-assisted stress corrosion cracking of metallic materials in LWRs, or advanced reactors concepts.

Prof. Dr. Miao Song
Guest Editor

Manuscript Submission Information

Manuscripts should be submitted online at www.mdpi.com by registering and logging in to this website. Once you are registered, click here to go to the submission form. Manuscripts can be submitted until the deadline. All submissions that pass pre-check are peer-reviewed. Accepted papers will be published continuously in the journal (as soon as accepted) and will be listed together on the special issue website. Research articles, review articles as well as short communications are invited. For planned papers, a title and short abstract (about 100 words) can be sent to the Editorial Office for announcement on this website.

Submitted manuscripts should not have been published previously, nor be under consideration for publication elsewhere (except conference proceedings papers). All manuscripts are thoroughly refereed through a single-blind peer-review process. A guide for authors and other relevant information for submission of manuscripts is available on the Instructions for Authors page. Metals is an international peer-reviewed open access monthly journal published by MDPI.

Please visit the Instructions for Authors page before submitting a manuscript. The Article Processing Charge (APC) for publication in this open access journal is 2600 CHF (Swiss Francs). Submitted papers should be well formatted and use good English. Authors may use MDPI's English editing service prior to publication or during author revisions.

Keywords

  • structural materials
  • radiation damage
  • radiation effects
  • stress corrosion cracking
  • irradiation-assisted stress corrosion cracking

Published Papers (1 paper)

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Research

12 pages, 1524 KiB  
Article
Study of the Application Efficiency of Irradiation with Heavy Ions to Increase the Helium Swelling Resistance of BeO Ceramics
by Maxim V. Zdorovets, Dmitriy I. Shlimas, Artem L. Kozlovskiy and Daryn B. Borgekov
Metals 2022, 12(2), 307; https://doi.org/10.3390/met12020307 - 10 Feb 2022
Viewed by 1079
Abstract
This paper considers the possibilities of increasing radiation resistance to helium swelling of beryllium oxide ceramics due to preliminary irradiation with heavy ions. Interest in this topic is due to the possibility of using these ceramics as materials for inert matrices of nuclear [...] Read more.
This paper considers the possibilities of increasing radiation resistance to helium swelling of beryllium oxide ceramics due to preliminary irradiation with heavy ions. Interest in this topic is due to the possibility of using these ceramics as materials for inert matrices of nuclear fuel and structural materials reflectors of high-temperature reactors. The samples studied were irradiated in two stages, namely irradiation with heavy Ar8+, Kr15+, and Xe22+ ions with a fluence of 1012 ion/cm2 and subsequent irradiation with He2+ ions with a fluence of 5x1017 ion/cm2. The main parameters used to compare and determine radiation modification efficiency were the crystal-structure swelling degree, a decrease in the hardness, and wear resistance of ceramics after irradiation with He2+ ions. During the studies carried out, it was found that preliminary irradiation with heavy Ar8+, Kr15+, and Xe22+ ions leads to a significant increase in radiation swelling resistance, as well as to an increase in crack resistance and wear resistance. Full article
(This article belongs to the Special Issue Radiation Damage and Irradiation-Assisted Stress Corrosion Cracking of Metallic Materials for Reactor Applications)
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