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Nuclear Materials Fundamentals and Applications
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Nuclear Materials Fundamentals and Applications

A special issue of Materials (ISSN 1996-1944). This special issue belongs to the section "Energy Materials".

Deadline for manuscript submissions: 10 January 2025 | Viewed by 2773

Special Issue Editors

Dr. Zhoutong He

E-Mail Website
Guest Editor
Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China
Interests: molten salt reactor; nuclear graphite; irradiation effect; materials characterization
Dr. Min Liu

E-Mail Website
Guest Editor
Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-Sen University, Zhuhai 519082, China
Interests: irradiation damage; dislocations; He bubble; alloy; silicon carbide
Special Issues, Collections and Topics in MDPI journals
Dr. Wei Qi

E-Mail Website
Guest Editor
Ji Hua Laboratory, Foshan 528200, China
Interests: diamond-like carbon; nuclear graphite; theory and technology of tribology; surface/interface science and properties control in machinery

Special Issue Information

Dear Colleagues,

This Special Issue invites contributions focusing on advancements in materials of experimental, theoretical, and computational aspects for nuclear applications. The topics of the Special Issue include the materials of fuels, cladding, core structures, pressure vessels, moderator and control components for fission reactors, and the first walls, blankets, insulators, and magnets for fusion reactors. The Special Issue welcomes the subjects of the interaction of neutrons, plasmas, ion beams, electron beams and electromagnetic radiation with materials in nuclear systems. The neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes, and macroscopic properties, are also a major concern of this issue.

Dr. Zhoutong He
Dr. Min Liu
Dr. Wei Qi
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. Materials is an international peer-reviewed open access semimonthly 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

  • nuclear materials
  • irradiation effects
  • moderator and control components for fission reactors
  • fuel elements
  • pressure vessels
  • first wall materials

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Published Papers (2 papers)

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Research

14 pages, 3653 KiB  
Article
A Comparative Study on Force-Fields for Interstitial Diffusion in α-Zr and Zr Alloys
by Jing Li, Tan Shi, Chen Zhang, Ping Zhang, Shehu Adam Ibrahim, Zhipeng Sun, Yuanming Li, Chuanbao Tang, Qing Peng and Chenyang Lu
Materials 2024, 17(15), 3634; https://doi.org/10.3390/ma17153634 - 23 Jul 2024
Viewed by 747
Abstract
Interstitial diffusion is important for radiation defect evolution in zirconium alloys. This study employed molecular dynamics simulations to investigate interstitial diffusion in α-Zr and its alloys with 1.0 at.% Nb and 1.0 at.% Sn using a variety of interatomic potentials. Pronounced differences in [...] Read more.
Interstitial diffusion is important for radiation defect evolution in zirconium alloys. This study employed molecular dynamics simulations to investigate interstitial diffusion in α-Zr and its alloys with 1.0 at.% Nb and 1.0 at.% Sn using a variety of interatomic potentials. Pronounced differences in diffusion anisotropy were observed in pure Zr among the employed potentials. This was attributed to the considerable differences in migration barriers among the various interstitial configurations. The introduction of small concentrations of Nb and Sn solute atoms was found to significantly influence diffusion anisotropy by either directly participating in the diffusion process or altering the chemical environment around the diffusing species. Based on the moderate agreement of interstitial energetics in pure Zr, accurately describing interstitial diffusion in Zr alloys is expected to be more complex. This work underscores the importance of the careful validation and selection of interatomic potentials and highlights the need to understand the effects of solute atoms on interstitial diffusion. Full article
(This article belongs to the Special Issue Nuclear Materials Fundamentals and Applications)
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11 pages, 3845 KiB  
Article
In Situ Characterization of 17-4PH Stainless Steel by Small-Angle Neutron Scattering
by Shibo Yan, Zijun Wang, Tianfu Li, Zhong Chen, Xiaoming Du, Yuntao Liu, Dongfeng Chen, Kai Sun, Rongdeng Liu, Bing Bai, Xinfu He, Kaitai Liu and Shuanzhu Wang
Materials 2023, 16(16), 5583; https://doi.org/10.3390/ma16165583 - 11 Aug 2023
Cited by 3 | Viewed by 1206
Abstract
17-4PH martensitic steel is usually used as valve stems in nuclear power plants and it suffers from thermal aging embrittlement due to long-time service in a high-temperature and high-pressure environment. Here, we characterized the evolution of microstructures at the nano-scale in 17-4PH steel [...] Read more.
17-4PH martensitic steel is usually used as valve stems in nuclear power plants and it suffers from thermal aging embrittlement due to long-time service in a high-temperature and high-pressure environment. Here, we characterized the evolution of microstructures at the nano-scale in 17-4PH steel by in situ small-angle neutron scattering (SANS) with a thermo-mechanically coupled loading device. The device could set different temperatures and tensile so that an in situ SANS experiment could dynamically characterize the process of nanoscale structural changes. The results showed that with increasing thermal aging time, the ε-Cu phase precipitates and grows as the temperature is 475 °C and 590 °C, and the ε-Cu phase is spherical at 475 °C but became elongated cylinders at 590 °C. Moreover, the loading stress could aid in the growth of the ε-Cu phase at 475 °C. Full article
(This article belongs to the Special Issue Nuclear Materials Fundamentals and Applications)
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