Performance and Behaviour of Metallic Nuclear Fuels and Cladding Materials

A special issue of Metals (ISSN 2075-4701). This special issue belongs to the section "Corrosion and Protection".

Deadline for manuscript submissions: closed (31 August 2022) | Viewed by 4213

Special Issue Editor


E-Mail Website
Guest Editor
Nuclear Fuels Centre of Excellence, Department of Mechanical, Aerospace and Civil Engineering, University of Manchester, Oxford Road, Manchester M13 9PL, UK
Interests: nuclear fuel manufacture and characterization; nuclear materials; corrosion; oxidation; electron microscopy; radiation damage
Special Issues, Collections and Topics in MDPI journals

Special Issue Information

Dear Colleagues,

Metals, alloys and intermetallics are of high interest to the nuclear industry due to their extensive use in nuclear fuel assemblies. The development of novel metallic nuclear fuels, fuel claddings and coating materials is driving the deployment of accident tolerant fuel (ATF) technology into the current generation of nuclear power plants. In addition, new high-density metallic fuels (HDFs) offer the possibility of replacing highly enriched uranium fuel (HEU), which is currently used in test reactors, with lower-enriched fuels with the aim of reducing proliferation risks. However, through their deployment, these novel metallic fuels, cladding and coating materials may be exposed to high levels of radiation damage and burnup, high temperature environments and oxidative or corrosive atmospheres. This can occur during normal operation or in off-normal accident scenarios, particularly in water-cooled nuclear reactors. The design criteria for these ATF and HDF assemblies led to recent advances in: 

  • The development of new metallic uranium fuels, cladding materials and coating barriers;
  • The study of radiation damage degradation mechanisms on the materials’ microstructures and properties;
  • High-temperature mechanical and thermophysical characterisation
  • The development of an in-depth understanding of their oxidation behaviour under a variety of conditions - such as air and steam oxidation

All of the above are required to predict the in-service behaviour of future nuclear fuel assemblies. 

In this Special Issue of Metals, we encourage contributions that report on any of these areas, as well as submissions that report on any recent developments towards understanding the behaviour of metallic nuclear fuels and cladding materials for their application in current or advanced nuclear technologies.

Dr. Robert W. Harrison
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

  • nuclear fuel
  • metallic nuclear fuel
  • fuel cladding
  • radiation damage
  • oxidation
  • high temperature
  • kinetics
  • corrosion mechanisms

Published Papers (2 papers)

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

Research

15 pages, 6203 KiB  
Article
Effect of Reprocessing on Microstructure and Corrosion Resistance of Zr-Sn-Nb Alloy
by Zongpei Wu, Yuzhen Jia, Xun Dai and Wei Yi
Metals 2022, 12(11), 1822; https://doi.org/10.3390/met12111822 - 27 Oct 2022
Viewed by 1137
Abstract
To study the effect of reprocessing on the microstructure and corrosion resistance of Zr-Sn-Nb alloy, the original plates of Zr-Sn-Nb alloy were hot-rolled, cold-rolled and recrystallized to obtain the reprocessed plates. The microstructure of both plates was observed with a scanning electron microscope [...] Read more.
To study the effect of reprocessing on the microstructure and corrosion resistance of Zr-Sn-Nb alloy, the original plates of Zr-Sn-Nb alloy were hot-rolled, cold-rolled and recrystallized to obtain the reprocessed plates. The microstructure of both plates was observed with a scanning electron microscope (SEM), a transmission electron microscope (TEM) and electron backscattering diffraction (EBSD). The original plates and reprocessed plates were put into a static autoclave for 300 days in 360 °C/18.6 MPa water. The relationship between the microstructure and corrosion resistance of the Zr-Sn-Nb alloy was discussed. The coarse deformation grains with twins and fine recrystallized grains were obtained, and grain sizes became smaller. The Ostwald ripening of second phase particles (SPPs) happened, and the average size of SPPs increased. Some SPPs changed from an HCP structure to an FCC structure. Reprocessing made the transition advance, which is related to the accelerated evolution of cracks in the oxide film and the increase in metal-oxide film interface roughness. The deterioration of corrosion resistance is closely related to the change of grain size, SPP size and SPP structure. Full article
Show Figures

Figure 1

16 pages, 11670 KiB  
Article
Simplified Model of a High Burnup Spent Nuclear Fuel Rod under Lateral Impact Considering a Stress-Based Failure Criterion
by Seyeon Kim and Sanghoon Lee
Metals 2021, 11(10), 1631; https://doi.org/10.3390/met11101631 - 14 Oct 2021
Viewed by 2652
Abstract
The inventory of spent nuclear fuel (SNF) generated in nuclear power plants is continuously increasing, and it is very important to maintain the structural integrity of SNF for economical and efficient management. The cladding surrounding nuclear fuel must be protected from physical and [...] Read more.
The inventory of spent nuclear fuel (SNF) generated in nuclear power plants is continuously increasing, and it is very important to maintain the structural integrity of SNF for economical and efficient management. The cladding surrounding nuclear fuel must be protected from physical and mechanical deterioration, which causes fuel rod breakage. In this study, the material properties of the simplified beam model of a SNF rod were calibrated for a drop accident evaluation by considering the pellet–clad interaction (PCI) of the high burnup fuel rod. In a horizontal drop, which is the most damaging during a drop accident of SNF, the stress in the cladding caused by the inertia action of the pellets has a great effect on the integrity of the fuel rod. The failure criterion for SNF was selected as the membrane plus bending stress through stress linearization in the cross-sections through the thickness of the cladding. Because the stress concentration in the cladding around the vicinity of the pellet–pellet interface cannot be simulated in a simplified beam model, a stress correction factor is derived through a comparison of the simplified model and detailed model. The applicability of the developed simplified model is checked through dynamic impact simulations. The developed model can be used in cask level analyses and is expected to be usefully utilized to evaluate the structural integrity of SNF under transport and in storage conditions. Full article
Show Figures

Figure 1

Back to TopTop