Advanced Alloys for Nuclear Applications

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

Deadline for manuscript submissions: closed (1 December 2021) | Viewed by 3070

Special Issue Editors

Department of Materials Science and Engineering, The University of Sheffield, Sir Robert Hadfield Building, Mappin St, Sheffield, S1 3JD, UK
Interests: Radiation effects in materials; nuclear materials development; ion implantation; transmission electron microscopy; surface sensitive spectroscopy.

E-Mail Website
Guest Editor
Metallurgy at the Department of Materials, University of Manchester, Manchester M13 9PL, UK
Interests: alloy design;high-entropy alloys;novel refractory alloys; characterization of processing-microstructure-property relationships in steels

E-Mail Website
Guest Editor
Department of Materials Science and Engineering,The University of Sheffield, Western Bank, Sheffield S10 2TN, UK
Interests: high-temperature physical metallurgy;alloy design and manufacturing;high entropy alloys

Special Issue Information

Dear Colleagues,

The continued development of advanced nuclear reactor systems, such as Gen-IV fission and fusion reactors, has resulted in significant advances in novel alloy design. These advanced alloys will have to withstand extremes in, and not limited to, temperature, pressure, radiation, and corrosion, and there is often a requirement for them to comprise low-activation elements to limit nuclear waste generation. The material design criteria for advanced reactor systems have led to recent advances in applying computational design methods to novel alloy design; development of reduced activation alloys, including nano-oxide dispersion strengthened steels, refractory alloys, and compositionally complex alloys, including high-entropy alloys (HEAs); as well as advances in understanding radiation damage mechanisms, high-temperature deformation, and corrosion resistance in advanced alloys. In this Special Issue of Metals, we encourage contributions that report on any of these areas. The development of novel alloys is not limited to these areas, and we therefore invite the submission of papers reporting any recent research on the design and development of alloys specifically for application in nuclear technologies.

Dr. Amy Gandy
Dr. Ed Pickering
Dr. Kathy Christofidou
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

  • Alloy design
  • Alloy development
  • Advanced nuclear systems
  • Radiation damage
  • Corrosion resistance
  • High-temperature deformation

Published Papers (1 paper)

Order results
Result details
Select all
Export citation of selected articles as:

Research

17 pages, 7594 KiB  
Article
Solid-State Welding of the Nanostructured Ferritic Alloy 14YWT Using a Capacitive Discharge Resistance Welding Technique
by Calvin Robert Lear, Jonathan Gregory Gigax, Matthew M. Schneider, Todd Edward Steckley, Thomas J. Lienert, Stuart Andrew Maloy and Benjamin Paul Eftink
Metals 2022, 12(1), 23; https://doi.org/10.3390/met12010023 - 23 Dec 2021
Cited by 1 | Viewed by 2485
Abstract
Joining nanostructured ferritic alloys (NFAs) has proved challenging, as the nano-oxides that provide superior strength, creep resistance, and radiation tolerance at high temperatures tend to agglomerate, redistribute, and coarsen during conventional fusion welding. In this study, capacitive discharge resistance welding (CDRW)—a solid-state variant [...] Read more.
Joining nanostructured ferritic alloys (NFAs) has proved challenging, as the nano-oxides that provide superior strength, creep resistance, and radiation tolerance at high temperatures tend to agglomerate, redistribute, and coarsen during conventional fusion welding. In this study, capacitive discharge resistance welding (CDRW)—a solid-state variant of resistance welding—was used to join end caps and thin-walled cladding tubes of the NFA 14YWT. The resulting solid-state joints were found to be hermetically sealed and were characterized across the weld region using electron microscopy (macroscopic, microscopic, and nanometer scales) and nanoindentation. Microstructural evolution near the weld line was limited to narrow (~50–200 μm) thermo-mechanically affected zones (TMAZs) and to a reduction in pre-existing component textures. Dispersoid populations (i.e., nano-oxides and larger oxide particles) appeared unchanged by all but the highest energy and power CDRW condition, with this extreme producing only minor nano-oxide coarsening (~2 nm → ~5 nm Ø). Despite a minimal microstructural change, the TMAZs were found to be ~10% softer than the surrounding base material. These findings are considered in terms of past solid-state welding (SSW) efforts—cladding applications and NFA-like materials in particular—and in terms of strengthening mechanisms in NFAs and the potential impacts of localized temperature–strain conditions during SSW. Full article
(This article belongs to the Special Issue Advanced Alloys for Nuclear Applications)
Show Figures

Figure 1

Back to TopTop