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Metals
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Advances in Metallic Nuclear Reactor Materials
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Advances in Metallic Nuclear Reactor Materials

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

Deadline for manuscript submissions: closed (31 December 2024) | Viewed by 4083

Special Issue Editor

Prof. Dr. Shurong Ding

E-Mail Website
Guest Editor
Institute of Mechanics and Computational Engineering, Department of Aeronautics and Astronautics, Fudan University, Shanghai 200433, China
Interests: nuclear materials; irradiation effects; constitutive relations; multi-field coupling; multi-scale correlating behaviors; non-linear mechanics
Special Issues, Collections and Topics in MDPI journals

Special Issue Information

Dear Colleagues,

Metallic nuclear materials, including metallic nuclear fuels and nuclear structural materials, have promising applications in many advanced nuclear reactors and in space nuclear power systems due to their inherent material characteristics. Metallic-material-based composite nuclear materials can also be used in high-flux reactors to produce isotopic neutron sources, contributing to the development of nuclear medicine. Due to the extreme, high-temperature, high-pressure environment and the neutron irradiation in nuclear reactors, metallic materials experience complicated multi-field coupling behaviors, such as thermal–mechanical–chemical coupling. To better promote the development and application of metallic nuclear reactor materials, it is vital to fully understand their material characteristics and evolutionary behaviors during in-reactor service.

In this Special Issue, we welcome articles and reviews that contribute to the development of metallic nuclear reactor materials, including theoretical, computational, and experimental studies. This is an excellent opportunity for scholars all over the world to publish their latest research and comprehensive reviews. We look forward to receiving your contributions.

Prof. Dr. Shurong Ding
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

  • metallic materials
  • nuclear reactors
  • irradiation effects
  • material properties
  • complex behaviors in service

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Published Papers (2 papers)

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Research

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26 pages, 5376 KiB  
Article
Modeling of Zirconium Atom Redistribution and Phase Transformation Coupling Behaviors in U-10Zr-Based Helical Cruciform Fuel Rods under Irradiation
by Xingdi Chen, Zhexiao Xie, Xiaoxiao Mao and Shurong Ding
Metals 2024, 14(7), 745; https://doi.org/10.3390/met14070745 - 24 Jun 2024
Viewed by 1593
Abstract
Uranium–zirconium metal-based Helical Cruciform Fuels (HCFs) have shown a promising prospect for their use in advanced nuclear reactors. However, during irradiation, dual-phase coexistence and the spatial heterogeneous distribution of zirconium atoms occur at higher powers, affecting the thermo-mechanical coupling behaviors and safety of [...] Read more.
Uranium–zirconium metal-based Helical Cruciform Fuels (HCFs) have shown a promising prospect for their use in advanced nuclear reactors. However, during irradiation, dual-phase coexistence and the spatial heterogeneous distribution of zirconium atoms occur at higher powers, affecting the thermo-mechanical coupling behaviors and safety of fuel elements and assemblies. In this study, based on the phase-field approach, the coupled multi-field governing equations to describe the zirconium diffusion and phase evolution for U-Zr metallic fuels are improved. Furthermore, the corresponding numerical algorithms and procedures for multi-field coupling calculations are developed. The numerical predictions of zirconium atom fraction are in good agreement with the relevant experimental results, validating the developed models, algorithms and programs. The zirconium atom redistribution and phase transformation coupling behaviors in high-power U-10wt%Zr-based HCF rods are also obtained. Moreover, the complex evolution mechanisms of multi-field variables are analyzed. The results indicate the following: (1) the irradiation enhancement of the thermal mobility and chemical mobility plays a critical role in the redistribution of Zr atoms; (2) the multi-field results of HCF rods have helical symmetric characteristics; (3) the contribution competitions of the temperature gradient and chemical potential gradient within the α phase and γ phase significantly influence the zirconium-atom redistribution, with the zirconium-rich zones formed in the elbow region and the zirconium-poor zones appearing inside. These research efforts supply a foundation for the further involvement of mechanical fields in multi-field coupling computation. Full article
(This article belongs to the Special Issue Advances in Metallic Nuclear Reactor Materials)
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Review

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22 pages, 10489 KiB  
Review
A Brief Review of the Impact of Neutron Irradiation Damage in Tungsten and Its Alloys
by Adil Wazeer, Tanner McElroy, Benjamin Thomas Stegman, Anyu Shang, Yifan Zhang, Vaibhav Singh, Huan Li, Zhongxia Shang, Haiyan Wang, Yexiang Xue, Guang Lin, Tim Graening, Xiao-Ying Yu and Xinghang Zhang
Metals 2024, 14(12), 1374; https://doi.org/10.3390/met14121374 - 1 Dec 2024
Viewed by 1783
Abstract
Neutron irradiation poses a substantial challenge in the development and application of tungsten (W) and its alloys, predominantly in the framework of nuclear fusion and fission environments. Although W is well-acknowledged for its unique properties like its high melting temperature and higher resistance [...] Read more.
Neutron irradiation poses a substantial challenge in the development and application of tungsten (W) and its alloys, predominantly in the framework of nuclear fusion and fission environments. Although W is well-acknowledged for its unique properties like its high melting temperature and higher resistance to sputtering, transmutation products, such as Re and Os, form and impact the alloy properties as a result of neutron irradiation. This transmutation effect accompanied by significant microstructure damage due to neutron irradiation can lead to the significant degradation of mechanical properties. This review surveys the literature focusing on the microstructural modifications post-irradiation and its impacts on the irradiation hardening. This review provides insights into the elaborative understanding on the neutron radiation damage on W and W alloys by exploring the microstructural evolution and hardness changes post-irradiation. The gaps and future opportunities for understanding neutron radiation damage in W are briefly summarized Full article
(This article belongs to the Special Issue Advances in Metallic Nuclear Reactor Materials)
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