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Materials Researches for Advanced Nuclear Energy
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Materials Researches for Advanced Nuclear Energy

A special issue of Energies (ISSN 1996-1073). This special issue belongs to the section "D1: Advanced Energy Materials".

Deadline for manuscript submissions: closed (8 May 2023) | Viewed by 7478

Special Issue Editor

Dr. Malin Liu

E-Mail Website
Guest Editor
Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084, China
Interests: advanced nuclear fuel design, fabrication and evaluation; advanced nuclear reactor; nuclear fuel materials; FB-CVD; multiphase flow; CFD-DEM simulation methods; ECT; particle tracking measurement technology; chemical reaction engineering in nuclear materials

Special Issue Information

Dear Colleagues,

With the rapid development of low-carbon energy demand, nuclear energy has drawn much attention in recent years, especially the inherent safety of advanced nuclear energy is focused on. Besides, the small and smart nuclear reactors for different aims, such as space nuclear reactors, mobile nuclear reactors, and so on are reported in many places. Generally speaking, the material research is the first step and essential part of the above investigation of kinds of advanced nuclear energy with the aim of extremely high temperature, inherent safety, smartness and mobile. There are also many researchers who are working in this area: promoting the nuclear energy application through materials updating and improvement. 

This Special Issue aims to present and disseminate the most recent advances related to the theory, design, fabrication, modeling, simulation, application and properties measurement of all types of nuclear fuels, especially for advanced nuclear energy in recent years.

Topics of interest for publication include, but are not limited to:

All aspects of nuclear materials for advanced nuclear energy, such as nuclear fission materials, nuclear fusion materials, materials used in different kinds of nuclear reactors, experimental research and numerical simulations, design and fabrication, production and properties evaluation, and so on.

Dr. Malin Liu
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. Energies 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 fuel
  • nuclear materials
  • nuclear fuel cycle
  • nuclear fusion materials
  • nuclear fission materials
  • nuclear fuel design
  • nuclear fuel fabrication
  • nuclear fuel evaluation
  • uranium related materials
  • advanced nuclear reactor
  • coating
  • assembly
  • cladding
  • nuclear fuel properties simulation
  • computational nuclear materials science
  • irradiation
  • PIE
  • ATF

Published Papers (3 papers)

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Research

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9 pages, 8484 KiB  
Communication
Molecular Dynamics Simulation of High Temperature Mechanical Properties of Nano-Polycrystalline Beryllium Oxide and Relevant Experimental Verification
by Ming-Dong Hou, Xiang-Wen Zhou, Malin Liu and Bing Liu
Energies 2023, 16(13), 4927; https://doi.org/10.3390/en16134927 - 25 Jun 2023
Cited by 2 | Viewed by 1263
Abstract
This article investigated the deformation behavior of nano-polycrystalline beryllium oxide under tensile and compressive stress using the molecular dynamics simulation method. Both the tensile and compressive test results indicate that beryllium oxide breaks mainly along grain boundaries. At low temperature, there is little [...] Read more.
This article investigated the deformation behavior of nano-polycrystalline beryllium oxide under tensile and compressive stress using the molecular dynamics simulation method. Both the tensile and compressive test results indicate that beryllium oxide breaks mainly along grain boundaries. At low temperature, there is little internal deformation of beryllium oxide grains. When the temperature is above 1473 K, the internal deformation of beryllium oxide grains also occurs, and the phenomenon becomes more obvious with the increase in temperature. This deformation within the grain should be plastic. The flexural strength fracture morphology of beryllium oxide also shows that the fracture mode of beryllium oxide is a brittle fracture at low temperature, while the slip bands appear at 1773 K. This indicates that beryllium oxide, as a ceramic material, can also undergo plastic deformation under high temperature and stress. Full article
(This article belongs to the Special Issue Materials Researches for Advanced Nuclear Energy)
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17 pages, 4911 KiB  
Article
Assessment of Accident-Tolerant Fuel with FeCrAl Cladding Behavior Using MELCOR 2.2 Based on the Results of the QUENCH-19 Experiment
by Tereza Abrman Marková, Guglielmo Lomonaco, Guido Mazzini and Martin Ševeček
Energies 2023, 16(6), 2763; https://doi.org/10.3390/en16062763 - 16 Mar 2023
Viewed by 1481
Abstract
To ensure the applicability of accident-tolerant fuels, their behaviors under various accidental conditions must be assessed. While the dependences of the behavior of single physical parameters can be investigated in single- or separate-effect experiments, and more complex phenomena can be investigated using integral-effect [...] Read more.
To ensure the applicability of accident-tolerant fuels, their behaviors under various accidental conditions must be assessed. While the dependences of the behavior of single physical parameters can be investigated in single- or separate-effect experiments, and more complex phenomena can be investigated using integral-effect tests, the behavior of an entire system as complex as a nuclear power plant core must be investigated using computer code modeling. One of the most commonly used computer codes for the assessment of severe accidents is MELCOR 2.2. In version 18019, the authors enabled the modeling of the behavior of the nuclear fuel with FeCrAl cladding (namely, alloy B136Y3) for the first time, using the GOX model. The ability of this model to reasonably accurately predict the behavior of FeCrAl cladding in accident conditions with quenching was verified in this work by modeling the QUENCH-19 experiment carried out in the Karlsruhe Institute of Technology on the QUENCH experimental device and by subsequent comparison of the MELCOR calculation results with the experiment. This article proves that the GOX model can be used to evaluate the behavior of FeCrAl cladding and that the results can be considered conservative. Full article
(This article belongs to the Special Issue Materials Researches for Advanced Nuclear Energy)
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Review

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24 pages, 7676 KiB  
Review
Molecular Dynamics Simulation Studies of Properties, Preparation, and Performance of Silicon Carbide Materials: A Review
by Zefan Yan, Rongzheng Liu, Bing Liu, Youlin Shao and Malin Liu
Energies 2023, 16(3), 1176; https://doi.org/10.3390/en16031176 - 20 Jan 2023
Cited by 14 | Viewed by 4151
Abstract
Silicon carbide (SiC) materials are widely applied in the field of nuclear materials and semiconductor materials due to their excellent radiation resistance, thermal conductivity, oxidation resistance, and mechanical strength. The molecular dynamics (MD) simulation is an important method to study the properties, preparation, [...] Read more.
Silicon carbide (SiC) materials are widely applied in the field of nuclear materials and semiconductor materials due to their excellent radiation resistance, thermal conductivity, oxidation resistance, and mechanical strength. The molecular dynamics (MD) simulation is an important method to study the properties, preparation, and performance of SiC materials. It has significant advantages at the atomic scale. The common potential functions for MD simulations of silicon carbide materials were summarized firstly based on extensive literatures. The key parameters, complexity, and application scope were compared and analyzed. Then, the MD simulation of SiC properties, preparation, and performance was comprehensively overviewed. The current studies of MD simulation methods and applications of SiC materials were systematically summarized. It was found that the Tersoff potential was the most widely applied potential function for the MD simulation of SiC materials. The construction of more accurate potential functions for special application fields was an important development trend of potential functions. In the MD simulation of SiC properties, the thermal properties and mechanical properties, including thermal conductivity, hardness, elastic modulus, etc., were mainly studied. The correlation between MD simulations of microscopic processes and the properties of macroscopic materials, as well as the methods for obtaining different property parameters, were summarized. In the MD simulation of SiC preparation, ion implantation, polishing, sputtering, deposition, crystal growth, amorphization, etc., were mainly studied. The chemical vapor deposition (CVD) and sintering methods commonly applied in the preparation of SiC nuclear materials were reported rarely and needed to be further studied. In the MD simulation of SiC performance, most of the present studies were related to SiC applications in the nuclear energy research. The irradiation damage simulation in the field of nuclear materials was studied most widely. It can be found that SiC materials in the field of nuclear materials study were a very important topic. Finally, the future perspective of MD simulation studies of SiC materials were given, and development suggestions were summarized. This paper is helpful for understanding and mastering the general method of computation material science aimed at the multi-level analysis. It also has a good reference value in the field of SiC material study and MD method study. Full article
(This article belongs to the Special Issue Materials Researches for Advanced Nuclear Energy)
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