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Advanced Examinations, Methods, and Tools for the Performance Analysis of Nuclear Fuel Systems

A special issue of Energies (ISSN 1996-1073). This special issue belongs to the section "B4: Nuclear Energy".

Deadline for manuscript submissions: 14 August 2024 | Viewed by 1014

Special Issue Editors


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Guest Editor
Idaho National Laboratory, Idaho Falls, ID, USA
Interests: nuclear fuel; nuclear energy; nuclear engineering; post-irradiation examination; nuclear fuel performance

E-Mail Website
Guest Editor
Idaho National Laboratory, Idaho Falls, ID, USA
Interests: nuclear fuel; cladding and structure materials; waste form; TEM; fuel performance; microstructure characterization

E-Mail Website
Guest Editor
Idaho National Laboratory, Idaho Falls, ID, USA
Interests: nuclear fuel development; irradiation testing; fabrication; characterisation; post-irradiation examination; modeling

Special Issue Information

Dear Colleagues,

Nuclear energy is the backbone of low-carbon electricity generation. Nuclear fuel provides a source of energy via fission reactions, which split uranium or plutonium fissile atoms to produce energy. The sequent energy transfer from nuclear energy to thermal energy creates thermal–mechanical effects, as well as radiation damages to nuclear fuel systems (here intended as nuclear fuel and cladding materials). A fundamental understanding and quantification of the abovementioned effects is at the heart of fuel performance analysis, particularly with regard to studying new nuclear fuel systems and qualifying them, or expanding the operating conditions of commercially employed products. Synergistically and complementary efforts from advanced examinations, methods and tools can fundamentally change our approach to understanding the underlying mechanisms of nuclear fuel performance and accelerating the discovery of new viable nuclear fuel systems. Other emerging techniques, such as domain knowledge-informed and scientific-data-driven artificial intelligence and machine learning, are becoming also essential.

This Special Issue welcomes contributions that attend to topics including, but not limited to, the following:

  • Innovative approaches to experimental examinations applied to nuclear fuel system performance;
  • Multiscale experimental examinations applied to nuclear fuel systems (irradiated and as fabricated);
  • Multiscale modelling and advanced methods;
  • Experimental and modeling verification and validation for nuclear fuel systems;
  • Domain-knowledge-informed and scientific-data-driven artificial intelligence, machine learning, and deep learning applied to nuclear fuel system performance analysis.

Dr. Luca Capriotti
Dr. Tiankai Yao
Dr. Pavel Medvedev
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. 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
  • fuel performance
  • fuel performance analysis
  • advanced methods

Published Papers (1 paper)

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Research

15 pages, 30937 KiB  
Article
Multi-Scale Characterization of Porosity and Cracks in Silicon Carbide Cladding after Transient Reactor Test Facility Irradiation
by Fei Xu, Tiankai Yao, Peng Xu, Jason L. Schulthess, Mario D. Matos II, Sean Gonderman, Jack Gazza, Joshua J. Kane and Nikolaus L. Cordes
Energies 2024, 17(1), 197; https://doi.org/10.3390/en17010197 - 29 Dec 2023
Viewed by 733
Abstract
Silicon carbide (SiC) ceramic matrix composite (CMC) cladding is currently being pursued as one of the leading candidates for accident-tolerant fuel (ATF) cladding for light water reactor applications. The morphology of fabrication defects, including the size and shape of voids, is one of [...] Read more.
Silicon carbide (SiC) ceramic matrix composite (CMC) cladding is currently being pursued as one of the leading candidates for accident-tolerant fuel (ATF) cladding for light water reactor applications. The morphology of fabrication defects, including the size and shape of voids, is one of the key challenges that impacts cladding performance and guarantees reactor safety. Therefore, quantification of defects’ size, location, distribution, and leak paths is critical to determining SiC CMC in-core performance. This research aims to provide quantitative insight into the defect’s distribution under multi-scale characterization at different length scales before and after different Transient Reactor Test Facility (TREAT) irradiation tests. A non-destructive multi-scale evaluation of irradiated SiC will help to assess critical microstructural defects from production and/or experimental testing to better understand and predict overall cladding performance. X-ray computed tomography (XCT), a non-destructive, data-rich characterization technique, is combined with lower length scale electronic microscopic characterization, which provides microscale morphology and structural characterization. This paper discusses a fully automatic workflow to detect and analyze SiC-SiC defects using image processing techniques on 3D X-ray images. Following the XCT data analysis, advanced characterizations from focused ion beam (FIB) and transmission electron microscopy (TEM) were conducted to verify the findings from the XCT data, especially quantitative results from local nano-scale TEM 3D tomography data, which were utilized to complement the 3D XCT results. In this work, three SiC samples (two irradiated and one unirradiated) provided by General Atomics are investigated. The irradiated samples were irradiated in a way that was expected to induce cracking, and indeed, the automated workflow developed in this work was able to successfully identify and characterize the defects formation in the irradiated samples while detecting no observed cracking in the unirradiated sample. These results demonstrate the value of automated XCT tools to better understand the damage and damage propagation in SiC-SiC structures for nuclear applications. Full article
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