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Special Issue "Advanced Characterization Techniques on Nuclear Fuels and Materials"

A special issue of Materials (ISSN 1996-1944). This special issue belongs to the section "Advanced Materials Characterization".

Deadline for manuscript submissions: 20 December 2023 | Viewed by 2667

Special Issue Editors

1. Micron School of Materials Science and Engineering, Boise State University, Boise, ID 83401, USA
2. Center for Advanced Energy Studies, Idaho Falls, ID 83401, USA
Interests: nanoscale structural and chemistry characterization achieved by the combination of transmission electron microscopy (TEM) and atom probe tomography (APT) techniques; material design, synthesis, property analysis; nanoscale structure and chemistry characterization; establishing critical connections between structure, chemistry and behavior at nanometric to atomic level through combinational TEM and APT techniques in a large range of various material systems from nanostructured magnetic materials, semiconductors, ceramics, quasicrystals, carbon nanotubes, and nuclear materials
1. Advanced Materials Laboratory, Boise State University, Boise, ID 83401, USA
2. Center for Advanced Energy Studies, Idaho Falls, ID 83401, USA
Interests: nuclear materials for extreme environment; radiation damage; electron microscopy; mechanical properties; advanced manufacturing

Special Issue Information

Dear Colleages,

The advancement of characterization techniques drives the fundamental understanding of materials science. Innovative techniques can reveal information that cannot be observed or lost in conventional methods. The application of modern techniques provides unique microstructural and chemical information down to the atomic scale. For nuclear application materials, the extreme environment in a nuclear reactor possesses significant challenges for characterization due to the combination of stress, corrosion, high temperature, and radiation. Therefore, research on nuclear fuels and structure materials requires advanced characterization techniques to investigate the material properties and verify the material performance in a nuclear reactor. This Special Issue highlights the world-leading capabilities and application of state-of-the-art characterization and micro-scale mechanical testing techniques to explore nuclear fuels and materials, including but not limited to advanced transmission electron microscopy, atom probe tomography, focused ion beam, nanoindenter and in situ testing techniques.

Contributing papers are solicited in the following areas:

  • Nuclear fuels and structure materials;
  • Microstructure characterization on non-irradiated and irradiated materials (ion-, proton- and neutron-irradiated);
  • In situ irradiation and post-irradiation examination (PIE) utilizing advanced characterization techniques, including but not limited to transmission electron microscopy (TEM), scanning transmission electron microscopy (STEM), high-resolution TEM (HRTEM), high-resolution STEM (HRSTEM), monochromated, probe-corrected, image-corrected (S)TEM, energy-dispersive X-ray spectroscopy (EDS), electron energy loss spectroscopy (EELS), energy-filtered TEM (EFTEM), precession electron diffraction (PED), atom probe tomography (APT), scanning electron microscopy (SEM), focused ion beam (FIB), electron backscattered diffraction (EBSD), X-ray powder diffraction (XRD), etc.;
  • In situ mechanical testing combined with TEM and/or SEM techniques, e.g., picoindenter;
  • Ex situ mechanical testing techniques, e.g., nanoindentation, microhardness testing.

Dr. Yaqiao Wu
Dr. Ching-Heng Shiau
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. Materials 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 fuels
  • nuclear structure materials
  • irradiation
  • post-irradiation examination
  • advanced microstructure characterization techniques
  • (scanning) transmission electron microscopy ((S)TEM)
  • atom probe tomography
  • in situ/ex situ mechanical testing

Published Papers (4 papers)

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Research

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Article
Investigation of Deformation Behavior of Additively Manufactured AISI 316L Stainless Steel with In Situ Micro-Compression Testing
Materials 2023, 16(17), 5980; https://doi.org/10.3390/ma16175980 - 31 Aug 2023
Viewed by 313
Abstract
Additive manufacturing techniques are being used more and more to perform the precise fabrication of engineering components with complex geometries. The heterogeneity of additively manufactured microstructures deteriorates the mechanical integrity of products. In this paper, we printed AISI 316L stainless steel using the [...] Read more.
Additive manufacturing techniques are being used more and more to perform the precise fabrication of engineering components with complex geometries. The heterogeneity of additively manufactured microstructures deteriorates the mechanical integrity of products. In this paper, we printed AISI 316L stainless steel using the additive manufacturing technique of laser metal deposition. Both single-phase and dual-phase substructures were formed in the grain interiors. Electron backscatter diffraction and energy-dispersive X-ray spectroscopy indicate that Si, Mo, S, Cr were enriched, while Fe was depleted along the substructure boundaries. In situ micro-compression testing was performed at room temperature along the [001] orientation. The dual-phase substructures exhibited lower yield strength and higher Young’s modulus compared with single-phase substructures. Our research provides a fundamental understanding of the relationship between the microstructure and mechanical properties of additively manufactured metallic materials. The results suggest that the uneven heat treatment in the printing process could have negative impacts on the mechanical properties due to elemental segregation. Full article
(This article belongs to the Special Issue Advanced Characterization Techniques on Nuclear Fuels and Materials)
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Article
Thermomechanical Properties of Neutron Irradiated Al3Hf-Al Thermal Neutron Absorber Materials
Materials 2023, 16(16), 5518; https://doi.org/10.3390/ma16165518 - 08 Aug 2023
Viewed by 436
Abstract
A thermal neutron absorber material composed of Al3Hf particles in an aluminum matrix is under development for the Advanced Test Reactor. This metal matrix composite was fabricated via hot pressing of high-purity aluminum and micrometer-size Al3Hf powders at volume [...] Read more.
A thermal neutron absorber material composed of Al3Hf particles in an aluminum matrix is under development for the Advanced Test Reactor. This metal matrix composite was fabricated via hot pressing of high-purity aluminum and micrometer-size Al3Hf powders at volume fractions of 20.0, 28.4, and 36.5%. Room temperature tensile and hardness testing of unirradiated specimens revealed a linear relationship between volume fraction and strength, while the tensile data showed a strong decrease in elongation between the 20 and 36.5% volume fraction materials. Tensile tests conducted at 200 °C on unirradiated material revealed similar trends. Evaluations were then conducted on specimens irradiated at 66 to 75 °C to four dose levels ranging from approximately 1 to 4 dpa. Tensile properties exhibited the typical increase in strength and decrease in ductility with dose that are common for metallic materials irradiated at ≤0.4Tm. Hardness also increased with neutron dose. The difference in strength between the three different volume fraction materials was roughly constant as the dose increased. Nanoindentation measurements of Al3Hf particles in the 28.4 vol% material showed the expected trend of increased hardness with irradiation dose. Transmission electron microscopy revealed oxygen at the interface between the Al3Hf particles and aluminum matrix in the irradiated material. Scanning electron microscopy of the exterior surface of tensile tested specimens revealed that deformation of the material occurs via plastic deformation of the Al matrix, cracking of the Al3Hf particles, and to a lesser extent, tearing of the matrix away from the particles. The fracture surface of an irradiated 28.4 vol% specimen showed failure by brittle fracture in the particles and ductile tearing of the aluminum matrix with no loss of cohesion between the particles and matrix. The coefficient of thermal expansion decreased upon irradiation, with a maximum change of −6.3% for the annealed irradiated 36.5 vol% specimen. Full article
(This article belongs to the Special Issue Advanced Characterization Techniques on Nuclear Fuels and Materials)
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Article
Nanocluster Evolution in D9 Austenitic Steel under Neutron and Proton Irradiation
Materials 2023, 16(13), 4852; https://doi.org/10.3390/ma16134852 - 06 Jul 2023
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Abstract
Austenitic stainless steel D9 is a candidate for Generation IV nuclear reactor structural materials due to its enhanced irradiation tolerance and high-temperature creep strength compared to conventional 300-series stainless steels. But, like other austenitic steels, D9 is susceptible to irradiation-induced clustering of Ni [...] Read more.
Austenitic stainless steel D9 is a candidate for Generation IV nuclear reactor structural materials due to its enhanced irradiation tolerance and high-temperature creep strength compared to conventional 300-series stainless steels. But, like other austenitic steels, D9 is susceptible to irradiation-induced clustering of Ni and Si, the mechanism for which is not well understood. This study utilizes atom probe tomography (APT) to characterize the chemistry and morphology of Ni–Si nanoclusters in D9 following neutron or proton irradiation to doses ranging from 5–9 displacements per atom (dpa) and temperatures ranging from 430–683 °C. Nanoclusters form only after neutron irradiation and exhibit classical coarsening with increasing dose and temperature. The nanoclusters have Ni3Si stoichiometry in a Ni core–Si shell structure. This core–shell structure provides insight into a potentially unique nucleation and growth mechanism—nanocluster cores may nucleate through local, spinodal-like compositional fluctuations in Ni, with subsequent growth driven by rapid Si diffusion. This study underscores how APT can shed light on an unusual irradiation-induced nanocluster nucleation mechanism active in the ubiquitous class of austenitic stainless steels. Full article
(This article belongs to the Special Issue Advanced Characterization Techniques on Nuclear Fuels and Materials)
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Review

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Review
Recent Progress in Gd-Containing Materials for Neutron Shielding Applications: A Review
Materials 2023, 16(12), 4305; https://doi.org/10.3390/ma16124305 - 10 Jun 2023
Cited by 1 | Viewed by 755
Abstract
With the rising demand for nuclear energy, the storage/transportation of radioactive nuclear by-products are critical safety issues for humans and the environment. These by-products are closely related to various nuclear radiations. In particular, neutron radiation requires specific protection by neutron shielding materials due [...] Read more.
With the rising demand for nuclear energy, the storage/transportation of radioactive nuclear by-products are critical safety issues for humans and the environment. These by-products are closely related to various nuclear radiations. In particular, neutron radiation requires specific protection by neutron shielding materials due to its high penetrating ability to cause irradiation damage. Herein, a basic overview of neutron shielding is presented. Since gadolinium (Gd) has the largest thermal neutron capture cross-section among various neutron absorbing elements, it is an ideal neutron absorber for shielding applications. In the last two decades, there have been many newly developed Gd-containing (i.e., inorganic nonmetallic-based, polymer-based, and metallic-based) shielding materials developed to attenuate and absorb the incident neutrons. On this basis, we present a comprehensive review of the design, processing methods, microstructure characteristics, mechanical properties, and neutron shielding performance of these materials in each category. Furthermore, current challenges for the development and application of shielding materials are discussed. Finally, the potential research directions are highlighted in this rapidly developing field. Full article
(This article belongs to the Special Issue Advanced Characterization Techniques on Nuclear Fuels and Materials)
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Planned Papers

The below list represents only planned manuscripts. Some of these manuscripts have not been received by the Editorial Office yet. Papers submitted to MDPI journals are subject to peer-review.

Title: Characterization of crystal structure evolution in U-2wt.%Zr using neutron diffraction with particular focus on the beta-uranium phase
Authors: Sven C. Vogel; Mike Benson; Yi Xie; Jason Harp; Sven Rudin; Walter Williams
Affiliation: LANL, INL, ORNL, Purdue
Abstract: Studies of the U-Zr phase diagram are motivated by alloys such as U-10wt.%Zr being leading fuel candidates for sodium-cooled fast reactor due to high fissile density, high thermal conductivity, ease of fabrication, and good compatibility with coolants. In the Zr-lean part of the phase diagram, the occurrence of beta-uranium, with its large tetragonal unit cell containing 30 atoms, is reported. However, experimental characterizations of such alloys with diffraction methods are very rare. Here, we present results on thermal cycling of U-2Zr characterized by time-of-flight neutron powder diffraction, during which the beta-uranium phase was observed. The data is compared with results from U-0.5Ti, an analog to pure uranium with the addition of titanium atoms preventing the otherwise inevitable grain growth, inhibiting accurate characterization with diffraction methods.

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