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Mechanical Behavior and Radiation Response of Materials

A special issue of Materials (ISSN 1996-1944). This special issue belongs to the section "Metals and Alloys".

Deadline for manuscript submissions: 20 February 2025 | Viewed by 2084

Special Issue Editor


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Guest Editor
Oak Ridge National Laboratory, Oak Ridge, TN, USA
Interests: nuclear materials; radiation effects; electron microscopy

Special Issue Information

Dear Colleagues,

Several materials challenges must be addressed to further enhance the reliability, safety, and economics of nuclear energy. As future Generation IV fission and proposed fusion energy systems demand higher operating temperatures and doses, there is a pressing need for studies examining the radiation degradation effects on the material performance of both traditional and advanced materials in these extreme environments. This Special Issue is dedicated to comprehending irradiation effects on microstructural evolution and their impact on the mechanical properties of materials for nuclear systems. Submissions can include original research articles or review articles covering a wide range of topics, including, but not limited to, the following:

  • Material defects/precipitates and their influence on mechanical properties.
  • Understanding defect formation and evolution through experimental or modeling studies.
  • Deformation behavior and microstructural design for enhanced material performance.
  • Innovations in advanced manufacturing and artificial intelligence/machine learning (AI/ML) applications.
  • Small-scale testing and advanced characterization techniques for material analysis.

Dr. Yanru Lin
Guest Editor

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Keywords

  • nuclear materials
  • material characterization
  • radiation hardening and embrittlement
  • solute segregation and phase stability
  • irradiation creep
  • void swelling
  • high-temperature helium embrittlement

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Published Papers (3 papers)

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Research

20 pages, 20653 KiB  
Article
Cost-Effective Thermomechanical Processing of Nanostructured Ferritic Alloys: Microstructure and Mechanical Properties Investigation
by Yan-Ru Lin, Yajie Zhao, Yi-Feng Su and Thak Sang Byun
Materials 2024, 17(19), 4763; https://doi.org/10.3390/ma17194763 - 28 Sep 2024
Viewed by 485
Abstract
Nanostructured ferritic alloys (NFAs), such as oxide-dispersion strengthened (ODS) alloys, play a vital role in advanced fission and fusion reactors, offering superior properties when incorporating nanoparticles under irradiation. Despite their importance, the high cost of mass-producing NFAs through mechanical milling presents a challenge. [...] Read more.
Nanostructured ferritic alloys (NFAs), such as oxide-dispersion strengthened (ODS) alloys, play a vital role in advanced fission and fusion reactors, offering superior properties when incorporating nanoparticles under irradiation. Despite their importance, the high cost of mass-producing NFAs through mechanical milling presents a challenge. This study delves into the microstructure-mechanical property correlations of three NFAs produced using a novel, cost-effective approach combining severe plastic deformation (SPD) with the continuous thermomechanical processing (CTMP) method. Analysis using scanning electron microscopy (SEM)-electron backscatter diffraction (EBSD) revealed nano-grain structures and phases, while scanning transmission electron microscopy (STEM)-energy dispersive X-ray spectroscopy (EDS) quantified the size and density of Ti-N, Y-O, and Cr-O fine particles. Atom probe tomography (APT) further confirmed the absence of finer Y-O particles and characterized the chemical composition of the particles, suggesting possible nitride dispersion strengthening. Correlation of microstructure and mechanical testing results revealed that CTMP alloys, despite having lower nanoparticle densities, exhibit strength and ductility comparable to mechanically milled ODS alloys, likely due to their fine grain structure. However, higher nanoparticle densities may be necessary to prevent cavity swelling under high-temperature irradiation and helium gas production. Further enhancements in uniform nanoparticle distribution and increased sink strength are recommended to mitigate cavity swelling, advancing their suitability for nuclear applications. Full article
(This article belongs to the Special Issue Mechanical Behavior and Radiation Response of Materials)
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12 pages, 5748 KiB  
Article
Radiation Effects in Tungsten and Tungsten-Copper Alloys Treated with Compression Plasma Flows and Irradiated with He Ions
by Azamat Ryskulov, Vitaliy Shymanski, Igor Ivanov, Bauyrzhan Amanzhulov, Anastasia Dauhaliuk, Vladimir Uglov, Adilet Temir, Valiantsin Astashynski, Asset Sapar, Anton Kuzmitski and Yerulan Ungarbayev
Materials 2024, 17(18), 4442; https://doi.org/10.3390/ma17184442 - 10 Sep 2024
Viewed by 445
Abstract
The paper presents the results of studying the structure and phase state of tungsten and tungsten-copper alloy after pulsed action of compression plasma flows and irradiation with helium ions. The compression plasma flows were used to modify the surface layer of tungsten, as [...] Read more.
The paper presents the results of studying the structure and phase state of tungsten and tungsten-copper alloy after pulsed action of compression plasma flows and irradiation with helium ions. The compression plasma flows were used to modify the surface layer of tungsten, as well as to create an alloy based on tungsten and copper. Using scanning electron microscopy and X-ray structural analysis, the formation of radiation defects on the tungsten surface was detected in the form of local areas of exfoliation and destruction, which begin to form at helium ion irradiation doses of 2 × 1017 cm−2. It is shown that preliminary plasma treatment of the surface in the melting mode leads to the complete disappearance of surface radiation defects up to a dose of 2 × 1017 cm−2, which may be associated with the formation of a fine-crystalline grain structure, the intergranular boundaries of which serve as effective sinks for primary radiation defects. Full article
(This article belongs to the Special Issue Mechanical Behavior and Radiation Response of Materials)
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25 pages, 9502 KiB  
Article
Thermomechanical Processing for Improved Mechanical Properties of HT9 Steels
by Thak Sang Byun, David A. Collins, Timothy G. Lach, Jung Pyung Choi and Stuart A. Maloy
Materials 2024, 17(15), 3803; https://doi.org/10.3390/ma17153803 - 1 Aug 2024
Viewed by 774
Abstract
Thermomechanical processing (TMP) of ferritic–martensitic (FM) steels, such as HT9 (Fe–12Cr–1MoWV) steels, involves normalizing, quenching, and tempering to create a microstructure of fine ferritic/martensitic laths with carbide precipitates. HT9 steels are used in fast reactor core components due to their high-temperature strength and [...] Read more.
Thermomechanical processing (TMP) of ferritic–martensitic (FM) steels, such as HT9 (Fe–12Cr–1MoWV) steels, involves normalizing, quenching, and tempering to create a microstructure of fine ferritic/martensitic laths with carbide precipitates. HT9 steels are used in fast reactor core components due to their high-temperature strength and resistance to irradiation damage. However, traditional TMP methods for these steels often result in performance limitations under irradiation, including embrittlement at low temperatures (<~430 °C), insufficient strength and toughness at higher temperatures (>500 °C), and void swelling after high-dose irradiation (>200 dpa). This research aimed to enhance both fracture toughness and strength at high temperatures by creating a quenched and tempered martensitic structure with ultrafine laths and precipitates through rapid quenching and unconventional tempering. Mechanical testing revealed significant variations in strength and fracture toughness depending on the processing route, particularly the tempering conditions. Tailored TMP approaches, combining rapid quenching with limited tempering, elevated strength to levels comparable to nano-oxide strengthened ferritic alloys while preserving fracture toughness. For optimal properties in high-Cr steels for future reactor applications, this study recommends a modified tempering treatment, i.e., post-quench annealing at 500 °C or 600 °C for 1 h, possibly followed by a brief tempering at a slightly higher temperature. Full article
(This article belongs to the Special Issue Mechanical Behavior and Radiation Response of Materials)
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