Manufacture, Properties and Applications of Advanced Nuclear Alloys

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

Deadline for manuscript submissions: 28 February 2025 | Viewed by 1202

Special Issue Editor

Department of Nuclear Science and Technology, Nanjing University of Aeronautics and Astronautics, Nanjing 210016, China
Interests: nuclear fuel; fuel cladding; nuclear wasteform; materials characterization
Special Issues, Collections and Topics in MDPI journals

Special Issue Information

Dear Colleagues,

Rapid growth in nuclear energy consumption as well as the evolution of Gen-IV nuclear reactor technologies are noticeable trends and facilitate the development of new materials and technologies.  Advances in Nuclear-Application Metal Alloys, which include the development and characterization of the materials (potentially) used in advanced nuclear reactors, are the scope for this Special Issue.  From the beginning, the development of metallic fuel or structural materials for nuclear reactors has been of great significance for the safety and reliability of nuclear power plants. A reactor is designed to be used for several dozens of years under an extreme core environment. Designing alloys to withstand extreme environments, either high temperatures or strong irradiation, is a fundamental challenge for materials scientists. For the abovementioned reasons, the fabrication, characterization, and theoretical understanding of advanced nuclear fuels and structural materials regarding their thermo-mechanical property, the synergistic effect of temperature, corrosion, irradiation, and in-pile performance are critical to the future nuclear application of advanced superalloys.

In this Special Issue, we welcome articles that focus on the fabrication, characterization, and theoretical study of metallic fuel, advanced nuclear fuel cladding, and structural alloys in the field of advanced nuclear systems. The innovative study of additive manufacturing of superalloys for nuclear applications and multiscale research methods that bridge the microstructure– property relationship are of special interest.

Dr. Kun Yang
Guest Editor

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Keywords

  • nuclear fuel
  • structural alloys
  • structural characterization
  • fabrication process
  • in-pile performance
  • extreme environment
  • irradiation
  • corrosion

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Published Papers (2 papers)

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Research

21 pages, 6488 KiB  
Article
X-Ray Diffraction Line Broadening of Irradiated Zr-2.5Nb Alloys
by Malcolm Griffiths
Metals 2024, 14(12), 1446; https://doi.org/10.3390/met14121446 - 17 Dec 2024
Viewed by 262
Abstract
The evolution of the mechanical properties of Zr-2.5Nb pressure tubing during irradiation is dependent on dislocation loop densities that are represented by the broadening of X-ray diffraction lines. Empirical models for the integral breadth of the diffraction peaks as a function of operating [...] Read more.
The evolution of the mechanical properties of Zr-2.5Nb pressure tubing during irradiation is dependent on dislocation loop densities that are represented by the broadening of X-ray diffraction lines. Empirical models for the integral breadth of the diffraction peaks as a function of operating conditions have been developed to predict the mechanical properties of CANDU reactor pressure tubes as a function of fast neutron flux, time and temperature. Apart from predicting mechanical property changes based on integral breadth measurements, a new model has been developed to retrospectively deduce abnormal operating temperatures of ex-service pressure from the measured line broadening. The application of integral breadth measurements to assess mechanical properties and temperature variations in pressure tubes is described and discussed in terms of the implications for pressure tube integrity. Full article
(This article belongs to the Special Issue Manufacture, Properties and Applications of Advanced Nuclear Alloys)
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20 pages, 14745 KiB  
Article
High-Temperature Steam Oxidation and Surface Microstructure Evolution of Fe13Cr6Al(1–4)Mo0.15Y Alloys
by Wen Qi, Yingjie Qiao, Wangwei Ru, Xiaodong Wang, Xiaohong Zhang, Ting Zheng, Shiyu Du, Peng Wang and Kun Yang
Metals 2024, 14(11), 1229; https://doi.org/10.3390/met14111229 - 28 Oct 2024
Viewed by 671
Abstract
The current study investigated the microstructure evolution and anti-corrosion behavior of low Y doping alloys of Fe13Cr6Al(1–4)Mo0.15Y subjected to high-temperature steam (800 °C to 1300 °C). The results indicate that steam oxidation induces the growth of high-quality oxidation film that is thermodynamically driven, [...] Read more.
The current study investigated the microstructure evolution and anti-corrosion behavior of low Y doping alloys of Fe13Cr6Al(1–4)Mo0.15Y subjected to high-temperature steam (800 °C to 1300 °C). The results indicate that steam oxidation induces the growth of high-quality oxidation film that is thermodynamically driven, with rapid increases in the thickness from 800 °C to 1300 °C without film convolution and spallation. The film convolution and spallation were successfully suppressed through on-site formation of the high-temperature stable ternary crystalline phase (Y2Mo3O12) and decreasing of the thickness of α-Al2O3 oxidation film during the fabrication and oxidation scenario. The on-site steam oxidation rate has been significantly suppressed, with lower weight gain and less oxidizing film convolution than monolithic FeCrAlMo alloy, through the addition of a low concentration of Y. Full article
(This article belongs to the Special Issue Manufacture, Properties and Applications of Advanced Nuclear Alloys)
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