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Metals
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Effects of Irradiation on the Structure and Properties of Metal...
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Effects of Irradiation on the Structure and Properties of Metal Materials

A special issue of Metals (ISSN 2075-4701).

Deadline for manuscript submissions: closed (29 February 2024) | Viewed by 4663

Special Issue Editors

Dr. Jing Wang

E-Mail Website
Guest Editor
School of Materials Science and Engineering, Hefei University of Technology, Hefei 230000, China
Interests: nuclear materials; irradiation effects; hydrogen isotopes; tungsten; breeder materials
Dr. Yifan Zhang

E-Mail Website
Guest Editor
School of Materials Science and Engineering, Hefei University of Technology, Hefei 230000, China
Interests: nuclear materials; irradiation damage; transmission electron microscope

Special Issue Information

Dear Colleagues,

Radiation tolerance is important for the safe applications of materials in nuclear power generation, fusion energy, space exploration, high-energy physics experiments, and other fields. Radiation damage to metals and alloys usually begins with the production of Frenkel pairs, followed by the aggregation of excessive interstitial atoms (SIAs) and vacancies, resulting in the degradation of the material. Therefore, it is necessary to investigate the mechanism of the irradiation effect on the structure and properties of metals. We are pleased to announce the launch of this Special Issue entitled "Effects of Irradiation on the Structure and Properties of Metal Materials". The purpose of this issue is to provide comprehensive insight into the characterization of metal materials after irradiation with neutrons, ions and plasma.

It is our pleasure to invite you to submit your manuscript to this Special Issue.

Dr. Jing Wang
Dr. Yifan Zhang
Guest Editors

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

  • irradiation effects
  • tungsten
  • steel
  • vanadium
  • copper
  • characterization
  • defects

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Published Papers (3 papers)

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Research

14 pages, 2619 KiB  
Article
A Model for the Temperature Distribution in a Rolled Joint in a CANDU Reactor Exploiting the Decomposition of the β-Zr Phase
by Glenn A. McRae, Malcolm Griffiths and Christopher E. Coleman
Metals 2024, 14(6), 692; https://doi.org/10.3390/met14060692 - 11 Jun 2024
Cited by 1 | Viewed by 709
Abstract
A competing-rates model is presented to account for operational changes in the metastable β-Zr phase of the Zr-2.5Nb alloy used to make CANDU reactor pressure tubes and is used to predict temperature gradients at the outlet rolled joints using the decomposition of the [...] Read more.
A competing-rates model is presented to account for operational changes in the metastable β-Zr phase of the Zr-2.5Nb alloy used to make CANDU reactor pressure tubes and is used to predict temperature gradients at the outlet rolled joints using the decomposition of the β-Zr phase as a proxy for temperature. High temperatures decompose the β phase by enhancing the formation of small particles of ω and α phases. Fast neutron flux causes the ω and α phases to shrink. This process is assumed to depend on the total volume of the particles, because they are comparable to, or smaller than, the size of the neutron displacement cascades. The barrier energy for thermal growth was determined to be 2.43 eV, when an Arrhenius A factor of 1013/s was assumed. The cross section for (ω+α)-phase shrinkage is 24.5 barns for Zr-2.5Nb irradiated in CANDU reactors. Assuming that the shrinkage is dominated by the migration of self-interstitial point defects, a defect production efficiency of 1.4% was found. Full article
(This article belongs to the Special Issue Effects of Irradiation on the Structure and Properties of Metal Materials)
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11 pages, 4279 KiB  
Article
Microstructure Evolution and Effect on Deuterium Retention in TiC- and ZrC-Doped Tungsten under He+ Ion Irradiation
by Xiaoyu Ding, Jiahui Fang, Qiu Xu, Panpan Zhang, Haojie Zhang, Laima Luo, Yucheng Wu and Jianhua Yao
Metals 2023, 13(4), 783; https://doi.org/10.3390/met13040783 - 17 Apr 2023
Cited by 4 | Viewed by 1766
Abstract
Combining the advantages of a wet chemical method and spark plasma sintering, carbide-doped materials W-1wt%TiC and W-1wt%ZrC were prepared. Microstructural evolution in W-1wt%TiC and W-1wt%ZrC under irradiation of 5 keV He+ at 600 °C to fluences up to 5.0 × 1021 [...] Read more.
Combining the advantages of a wet chemical method and spark plasma sintering, carbide-doped materials W-1wt%TiC and W-1wt%ZrC were prepared. Microstructural evolution in W-1wt%TiC and W-1wt%ZrC under irradiation of 5 keV He+ at 600 °C to fluences up to 5.0 × 1021 ions/m2 with ion flux of about 8.8 × 1017 ions/m2s was investigated by transmission electron microscopy (TEM). The dislocation loop number density of W-1wt%TiC was higher than that of W-1wt%ZrC, but the average loop size of the W-1wt%TiC was in average smaller. There were no observable helium bubbles in W-1wt%TiC and W-1wt%ZrC, exhibiting higher radiation resistance to He+ compared to pure W. He+ pre-damaged and undamaged W-1wt%TiC and W-1wt%ZrC samples were irradiated by 5 keV D2+ to estimate the D retention in doped W materials. The irradiation damage impact of He+ on deuterium retention was examined by a method of thermal desorption spectroscopy (TDS). Compared with the undamaged samples, it was illustrated that D2 retention of W-1wt%TiC and W-1wt%ZrC increased after He+ pre-irradiation. Full article
(This article belongs to the Special Issue Effects of Irradiation on the Structure and Properties of Metal Materials)
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13 pages, 5877 KiB  
Article
Investigation of the Y Effect on the Microstructure Response and Radiation Hardening of PM V-4Cr-4Ti Alloys after Irradiation with D Ions
by Yifan Zhang, Xiaoyuan Sun, Bing Ma, Jing Wang, Laima Luo and Yucheng Wu
Metals 2023, 13(3), 541; https://doi.org/10.3390/met13030541 - 8 Mar 2023
Cited by 4 | Viewed by 1522
Abstract
In the current work, an analysis of the effects of Y on the radiation hardening and microstructure response of a V-4Cr-4Ti alloy has been conducted after 30 keV D ion irradiation at room temperature using transmission electron microscopy (TEM) and nanoindentation. The results [...] Read more.
In the current work, an analysis of the effects of Y on the radiation hardening and microstructure response of a V-4Cr-4Ti alloy has been conducted after 30 keV D ion irradiation at room temperature using transmission electron microscopy (TEM) and nanoindentation. The results show that the formation of large Y2O3 and small Y2V2O7 nanoparticles was confirmed, indicating that the addition of Y reduces the amount of dissolved oxygen. The addition of Y has been shown to affect the radiation-induced dislocation loops, radiation hardening, and Ti-rich segregation of the V-4Cr-4Ti alloy. With the addition of Y, the mean size of the radiation-induced dislocation loop decreased, which may result from the strong sink strength of the nanoparticle/matrix interface, interactions between Y atoms and SIA clusters, and the strong binding energy of vacancy–oxygen pairs. Some particles with core–shell structures were observed after ion irradiation, where Ti-rich segregations at the nanoparticle/matrix interface were confirmed. These results indicate that Y might promote abnormal segregation. Possible causes for this include the lower interface energy at the particle/matrix interface and the interaction between oxygen and solute atoms. Full article
(This article belongs to the Special Issue Effects of Irradiation on the Structure and Properties of Metal Materials)
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