Search for Articles:
Title / Keyword
Author / Affiliation / Email
Journal
Article Type
 
 
Advanced Search
 
Section
Special Issue
Volume
Issue
Number
Page
 
5.8
3.1
Journals
Materials
Special Issues
Structural Materials for Nuclear Applications
materials-logo
Submit to Materials Review for Materials Propose a Special Issue

Journal Menu

► Journal Menu

Journal Browser

► Journal Browser
share announcement

Structural Materials for Nuclear Applications

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

Deadline for manuscript submissions: closed (10 January 2023) | Viewed by 18779

Special Issue Editors

Prof. Dr. Linjiang Chai

E-Mail Website
Guest Editor
College of Materials Science and Engineering, Chongqing University of Technology, Chongqing 400054, China
Interests: high-energy beam (laser/electron beam) surface modification of metal materials (Zr and Ti); high-entropy alloy coatings; structure/texture/performance of HCP metals (Ti, Zr, Mg, etc.); materials characterization (EBSD, TKD, etc.)
Prof. Dr. Ning Guo

E-Mail Website
Guest Editor
Faculty of Materials and Energy, Southwest University, Chongqing 400715, China
Interests: metallic materials (ODS steels); gradient-structured materials; surface modification (steels); wear/corrosion behavior (steels); deformation/toughening mechanisms; materials characterization
Special Issues, Collections and Topics in MDPI journals

Special Issue Information

Dear Colleagues,

Nuclear energy has many advantages, including abundant reserves, high energy density, and good adaptability to harsh environments, which is an important part of the future low-carbon energy. The development of advanced nuclear energy systems with high safety and good economy is an important driving force for the long-term stable development of the global low-carbon economy. The development of structural materials suitable for high-temperature, high-radiation, and harsh corrosion environments is one of the keys to the successful implementation of advanced nuclear energy systems. In recent years, new zirconium alloys, FeCrAl, ODS alloys, advanced ceramics, and stainless steels have been rapidly developed. This Special Issue focuses on the composition, microstructure, properties, and preparation methods of such advanced structural materials for future nuclear systems.

Prof. Dr. Linjiang Chai
Prof. Dr. Ning Guo
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

  • steel
  • surface modification
  • deposition (physical, chemical, electrical)
  • spraying (thermal, plasma)
  • pulsed laser
  • pulsed electron beam
  • pack cementation

Benefits of Publishing in a Special Issue

  • Ease of navigation: Grouping papers by topic helps scholars navigate broad scope journals more efficiently.
  • Greater discoverability: Special Issues support the reach and impact of scientific research. Articles in Special Issues are more discoverable and cited more frequently.
  • Expansion of research network: Special Issues facilitate connections among authors, fostering scientific collaborations.
  • External promotion: Articles in Special Issues are often promoted through the journal's social media, increasing their visibility.
  • e-Book format: Special Issues with more than 10 articles can be published as dedicated e-books, ensuring wide and rapid dissemination.

Further information on MDPI's Special Issue policies can be found here.

Published Papers (6 papers)

Download All Papers
Order results
Result details
Show export options expand_more Show export options expand_less
Select all
Export citation of selected articles as:

Research

Jump to: Review

14 pages, 5603 KiB  
Article
The Effect of Cooling Rate on Crystallographic Features of Phase Transformations in Zr-2.5Nb
by Mikhail L. Lobanov, Valentin Yu. Yarkov, Vladimir I. Pastukhov, Inna A. Naschetnikova, Stepan I. Stepanov, Andrey A. Redikultsev and Mariya A. Zorina
Materials 2023, 16(10), 3758; https://doi.org/10.3390/ma16103758 - 16 May 2023
Cited by 5 | Viewed by 1792
Abstract
Zirconium (Zr) alloys are utilized as structural components for the cores of nuclear reactors due to the excellent combination of their mechanical properties and corrosion resistance under intense neutron irradiation conditions in water. The characteristics of microstructures formed during heat treatments play a [...] Read more.
Zirconium (Zr) alloys are utilized as structural components for the cores of nuclear reactors due to the excellent combination of their mechanical properties and corrosion resistance under intense neutron irradiation conditions in water. The characteristics of microstructures formed during heat treatments play a crucial role in obtaining the operational performance of parts made from Zr alloys. This study investigates the morphological features of (α + β)-microstructures in the Zr-2.5Nb alloy, as well as the crystallographic relationships between α- and β-phases. These relationships are induced by the β→α(α″) displacive transformation that occurs during water quenching (WQ) and the diffusion-eutectoid transformation that takes place during furnace cooling (FC). To conduct this analysis, samples solution treated at 920 °C were examined using EBSD and TEM. The experimental distribution of α/β-misorientations for both cooling regimes deviates from the Burgers orientation relationship (BOR) at a discrete set of angles close to 0, 29, 35, and 43°. The experimental α/β-misorientation spectra are confirmed by crystallographic calculations for the β→α→β-transformation path based on the BOR. Similar spectra of misorientation angle distribution in α-phase and between α and β phases in Zr-2.5Nb after WQ and FC point to similar transformation mechanisms and the significant role of shear and shuffle in β→α-transformation. Full article
(This article belongs to the Special Issue Structural Materials for Nuclear Applications)
►▼ Show Figures

Figure 1

17 pages, 15765 KiB  
Article
Compatibility of Different Commercial Alloys in High-Temperature, Supercritical Carbon Dioxide
by Gen Zhang, E Jiang, Weiwei Liu, Hong Yang, Yulong Wu and Yanping Huang
Materials 2022, 15(13), 4456; https://doi.org/10.3390/ma15134456 - 24 Jun 2022
Cited by 9 | Viewed by 1775
Abstract
In this work, the compatibility and long-term integrity of candidate structural materials, including the austenitic stainless steel 316NG, the Fe-Ni-based alloy 800H, and the Ni-based alloy 625, were tested in high-temperature and high-pressure SCO2. The exposure time was up to 3000 [...] Read more.
In this work, the compatibility and long-term integrity of candidate structural materials, including the austenitic stainless steel 316NG, the Fe-Ni-based alloy 800H, and the Ni-based alloy 625, were tested in high-temperature and high-pressure SCO2. The exposure time was up to 3000 h. The results showed that the corrosion kinetics approximately followed a near-cubic law for 316NG and 800H. After 3000 h exposure, all oxide layers, mainly composed of Cr2O3, were continuous, compact, and protective, and their thicknesses were about 21~45 nm, 64~88 nm, and 34~43 nm, respectively. In the case of carburization, dark spots corresponding carbon deposition were observed on the surface and a little enriched in the underside of the oxide for 800H. Moreover, the enrichment of trace elements was found at the oxide/substrate interface through GDOES and TEM analyses, i.e., the enrichment of Mn and Si for 316NG, the enrichment of Mn, Si, Al, and Ti for 800H, and the enrichment of Ti and Al for alloy 625. Full article
(This article belongs to the Special Issue Structural Materials for Nuclear Applications)
►▼ Show Figures

Figure 1

13 pages, 3735 KiB  
Article
Oxidation Behavior Characterization of Zircaloy-4 Cladding with Different Hydrogen Concentrations at 500–800 °C in an Ambient Atmosphere
by Tung-Yuan Yung, Wen-Fang Lu, Kun-Chao Tsai, Cheng-Hao Chuang and Po-Tuan Chen
Materials 2022, 15(9), 2997; https://doi.org/10.3390/ma15092997 - 20 Apr 2022
Cited by 3 | Viewed by 2586
Abstract
This study simulated the after-burned zirconium cladding oxidation in air at temperatures between 500 and 800 °C. The weight changes of Zircaloy-4 cladding with hydrogen contents of 100–1000 ppm continuously measured through thermogravimetric analysis (TGA) during oxidation tests at different temperatures in an [...] Read more.
This study simulated the after-burned zirconium cladding oxidation in air at temperatures between 500 and 800 °C. The weight changes of Zircaloy-4 cladding with hydrogen contents of 100–1000 ppm continuously measured through thermogravimetric analysis (TGA) during oxidation tests at different temperatures in an air atmosphere. The TGA results indicate a transition of oxidation kinetics from a parabolic rate law to a linear rate law for as-received and hydrided Zircaloy-4 cladding. The hydrogen concentration of Zircaloy-4 had a marked effect on its pre-transition oxidation in air between 500 and 800 °C. For all samples, the linear oxidation (post transition stage) at 650 °C, which is the critical oxidation temperature, displays a similar trend. In addition, scanning electron microscopy and transmission electron micros-copy examinations indicated the presence of a few and numerous discontinuous micro-cracks in the oxide layer in the pre-transition and post-transition stages, respectively. Full article
(This article belongs to the Special Issue Structural Materials for Nuclear Applications)
►▼ Show Figures

Figure 1

13 pages, 6125 KiB  
Article
Duplex Nucleation and Its Effect on the Grain Size and Properties of Near Eutectic Al-Si Alloys
by Wenbo Li, Yuying Wu, Yongjie Wu, Yang Li, Amanisha Ehti and Xiangfa Liu
Materials 2022, 15(7), 2507; https://doi.org/10.3390/ma15072507 - 29 Mar 2022
Cited by 2 | Viewed by 2143
Abstract
Duplex nucleation and its effect on the grain size and properties of near eutectic Al-Si alloys were investigated in this work. It is found that the grain size of Al-13Si-1Cu alloy can be greatly refined by addition of Al-2Ti-0.5B-0.5C and Al-P master alloys, [...] Read more.
Duplex nucleation and its effect on the grain size and properties of near eutectic Al-Si alloys were investigated in this work. It is found that the grain size of Al-13Si-1Cu alloy can be greatly refined by addition of Al-2Ti-0.5B-0.5C and Al-P master alloys, and TiB2/AlP duplex nucleation was observed at the nuclei of primary silicon in the process of studying the refinement mechanism. TiB2 phase coated by Al co-existed with AlP in the nuclei of primary Si. The existence of Al phase should not only guarantee the promotion of TiB2 particles on the nucleation of AlP particles, but also made TiB2 particle stable in the core of primary silicon through the interaction with the Si phase. Duplex nucleation can not only affect the grain size of Al-Si alloy, but also effect of the distribution of strengthening phases in Al-Si alloy and improve the properties. Compared with single Al-P master alloy treatment, the tensile strength of Al-12Si-4Cu-2Ni-1Mg alloy after duplex nucleation treatment are improved obviously. The fatigue performance of Al-12Si-4Cu-2Ni-1Mg alloy is also improved significantly by the duplex nucleation. Full article
(This article belongs to the Special Issue Structural Materials for Nuclear Applications)
►▼ Show Figures

Figure 1

14 pages, 8429 KiB  
Article
Effect of Al Concentration on Microstructure and Properties of AlNbTiZr Medium-Entropy Alloy Coatings
by Hongyang Xin, Jijun Yang, Jianjun Mao, Qingsong Chen, Jiaqi Yang, Wei Zhang, Zhien Ning, Changqing Teng, Cong Ma, Lu Wu and Xiaoyong Wu
Materials 2021, 14(24), 7661; https://doi.org/10.3390/ma14247661 - 12 Dec 2021
Cited by 12 | Viewed by 2723
Abstract
The AlNbTiZr medium-entropy alloy (MEA) coatings with different Al contents were prepared on N36 zirconium alloy substrates by RF magnetron co-sputtering. The morphology, microstructure, mechanical properties, surface wettability and corrosion resistance of the AlNbTiZr MEA coatings were studied to evaluate the surface protection [...] Read more.
The AlNbTiZr medium-entropy alloy (MEA) coatings with different Al contents were prepared on N36 zirconium alloy substrates by RF magnetron co-sputtering. The morphology, microstructure, mechanical properties, surface wettability and corrosion resistance of the AlNbTiZr MEA coatings were studied to evaluate the surface protection behavior of zirconium alloy cladding under operation conditions of a pressurized water reactor. The results showed that all the coatings were composite structures with amorphous and bcc-structured nanocrystals. With the increase of Al content, both the elastic modulus and hardness decreased first and then increased. The hydrophobicity of the coatings was enhanced compared with that of the substrate. The 10.2 at.% Al AlNbTiZr coating had the best corrosion resistance and the minimum oxygen penetration depth, which originated from the formation of a denser oxide layer consisting of Nb2Zr6O17 and ZrO2. This study provides an improved idea for the design and development of Al-containing MEA coating materials for accident tolerant fuel. Full article
(This article belongs to the Special Issue Structural Materials for Nuclear Applications)
►▼ Show Figures

Figure 1

Review

Jump to: Research

39 pages, 7879 KiB  
Review
Materials to Be Used in Future Magnetic Confinement Fusion Reactors: A Review
by René Alba, Roberto Iglesias and María Ángeles Cerdeira
Materials 2022, 15(19), 6591; https://doi.org/10.3390/ma15196591 - 22 Sep 2022
Cited by 20 | Viewed by 6912
Abstract
This paper presents the roadmap of the main materials to be used for ITER and DEMO class reactors as well as an overview of the most relevant innovations that have been made in recent years. The main idea in the EUROfusion development program [...] Read more.
This paper presents the roadmap of the main materials to be used for ITER and DEMO class reactors as well as an overview of the most relevant innovations that have been made in recent years. The main idea in the EUROfusion development program for the FW (first wall) is the use of low-activation materials. Thus far, several candidates have been proposed: RAFM and ODS steels, SiC/SiC ceramic composites and vanadium alloys. In turn, the most relevant diagnostic systems and PFMs (plasma-facing materials) will be described, all accompanied by the corresponding justification for the selection of the materials as well as their main characteristics. Finally, an outlook will be provided on future material development activities to be carried out during the next phase of the conceptual design for DEMO, which is highly dependent on the success of the IFMIF-DONES facility, whose design, operation and objectives are also described in this paper. Full article
(This article belongs to the Special Issue Structural Materials for Nuclear Applications)
►▼ Show Figures

Figure 1

Show export options expand_more Show export options expand_less
Select all
Export citation of selected articles as:
 
Displaying articles 1-6
Back to TopTop