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Experiment and Calculation Simulation to Study Hydrogen-Helium Effect Mechanism in Materials

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

Deadline for manuscript submissions: closed (20 December 2022) | Viewed by 7046

Special Issue Editor

Prof. Dr. Bingsheng Li

E-Mail Website
Guest Editor
State Key Laboratory for Environment-Friendly Energy Materials, Southwest University of Science and Technology, Mianyang 621010, China
Interests: ion irradiation; nuclear structural materials; corrosion

Special Issue Information

Dear Colleagues,

The behaviors of materials under strong neutron and hydrogen/helium radiation fields are key scientific issues in the development of advanced nuclear energy devices. Firstly, irradiation of neutron and hydrogen/helium does not only cause lattice defects, but also the formation of material bubbles and embrittlement and hardness of the material. Secondly, the thermal stress field induced by the temperature gradient on the surface of the materials will cause crack of the materials due to the high heat flow. Under such conditions, materials in nuclear facilities must not only have good mechanical properties, radiation resistance, and high capacity of heat resistance load, but also low hydrogen isotope and helium retention, etc. Therefore, it is urgent to develop materials from the perspective of the design, structure, and performance of anti-irradiation of hydrogen and helium ions. Fundamental research on the mechanism of hydrogen and helium ion radiation of materials seems particularly important. For this reason, we are putting forward this Special Issue on “Experiment and Calculation Simulation to Study the Hydrogen–Helium Effect Mechanism in Materials”. Experimental research focusing on radiation hardening, swelling, embrittlement, hydrogen and helium bubble size and density, and hydrogen and helium dynamics through mechanical performance and microstructure observation is invited. Simulation calculation and theoretical research focusing on retention of hydrogen and helium and different levels of structural evolution information under irradiation environment is also of interest.

This Special Issue of Materials aims at proposing possible ways to control hydrogen and helium, reduce radiation swelling, radiation hardening, and radiation embrittlement. Especially welcome are research papers that involved hydrogen and helium retention, hydrogen and helium blister formation, and hydrogen and helium-induced structure damage and evolution in the materials for fusion and fission applications. The journal accepts original research papers as well as review articles summarizing recent progress in the field.

Prof. Dr. Bingsheng Li
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. 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

  • ion irradiation
  • irradiation damage
  • hydrogen and helium
  • hydrogen retention
  • radiation swelling
  • radiation embrittlement

Published Papers (4 papers)

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Research

11 pages, 10278 KiB  
Article
Investigation of Nano-Scale Segregation in Nanostructured Ferritic Alloy 14YWT after Heavy Ion Irradiation
by Junfeng Cai, Wentuo Han, Farong Wan and Jianchao He
Materials 2022, 15(20), 7257; https://doi.org/10.3390/ma15207257 - 17 Oct 2022
Viewed by 1049
Abstract
Oxide-dispersion-strengthened (ODS) steels, which contain nano-scale Y-Ti-O particles, are being considered for high-temperature radiation environments of nuclear reactors. It is important to accurately characterize the structure of grain boundaries and understand the behavior of segregation at grain boundaries in ODS steels during irradiation. [...] Read more.
Oxide-dispersion-strengthened (ODS) steels, which contain nano-scale Y-Ti-O particles, are being considered for high-temperature radiation environments of nuclear reactors. It is important to accurately characterize the structure of grain boundaries and understand the behavior of segregation at grain boundaries in ODS steels during irradiation. The effect of heavy ion irradiation at 700 °C on Nanostructured Ferritic Alloy 14YWT was investigated using Atom Probe Tomography. Enrichment of Cr occurs at the grain boundaries as well as at nano oxide particle surfaces in the unirradiated sample. The enrichment of Ti and Y at a grain boundary corresponds with Y-Ti-O nano oxide particles with larger size compared to those in the grain, and the Cr enrichment is particularly accentuated at these larger nano oxide particles. The segregation of W occurs at the grain boundaries that are without nano oxide particles. O is segregated at grain boundaries without oxide particles after irradiation. The segregation behavior of Cr, W, Ti, and Y at the grain boundary in the irradiated samples is similar to that in the unirradiated sample. The nano oxide particles embedded in the grain boundary are a primary reason for the increase in Cr segregation at the grain boundary. Full article
(This article belongs to the Special Issue Experiment and Calculation Simulation to Study Hydrogen-Helium Effect Mechanism in Materials)
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12 pages, 2517 KiB  
Article
Investigation of Exfoliation Efficiency of 6H-SiC Implanted Sequentially with He+ and H2+ Ions
by Guoqiang You, Haipeng Lin, Yanfeng Qu, Jie Hao, Suyuan You and Bingsheng Li
Materials 2022, 15(8), 2941; https://doi.org/10.3390/ma15082941 - 18 Apr 2022
Viewed by 2027
Abstract
Silicon carbide (SiC) is a promising material used in the advanced semiconductor industry. Fabricating SiC-on-insulator via H implantation is a good method. He and H co-implantation into Si can efficiently enhance exfoliation efficiency compared to only H implantation. In this study, 6H-SiC single [...] Read more.
Silicon carbide (SiC) is a promising material used in the advanced semiconductor industry. Fabricating SiC-on-insulator via H implantation is a good method. He and H co-implantation into Si can efficiently enhance exfoliation efficiency compared to only H implantation. In this study, 6H-SiC single crystals were implanted with He+ and H2+ dual beams at room temperature, followed by annealing at 1100 °C for 15 min, and irradiations with 60 keV He ions with a fluence of 1.5 × 1016 ions/cm−2 or 5.0 × 1016 ions/cm−2 and 100 keV H2+ ions with a fluence of 5 × 1016 ions/cm−2 were carried out. The lattice disorder was characterized by both Raman spectroscopy and transmission electron microscopy. The intensity of Raman peaks decreased with increasing fluence. No Raman shift or new phases were found. A very high numerical density of bubbles was observed as compared to single H or He implantation. Moreover, stacking faults, Frank loops and tangled dislocations were formed in the damaged layer. Surface exfoliation was inhibited by co-implantation. A possible reason for this is an increase in fracture toughness and a decrease in elastic out-of-plane strain due to dense bubbles and stacking faults. Full article
(This article belongs to the Special Issue Experiment and Calculation Simulation to Study Hydrogen-Helium Effect Mechanism in Materials)
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12 pages, 2000 KiB  
Article
Influence of Alloy Atoms on Substitution Properties of Hydrogen by Helium in ZrCoH3
by Panpan Wang, Qilong Cao, Yuwei You, Xiangshan Kong, Xuebang Wu and Changsong Liu
Materials 2021, 14(21), 6704; https://doi.org/10.3390/ma14216704 - 7 Nov 2021
Cited by 2 | Viewed by 1548
Abstract
Intermetallic alloy ZrCo is a good material for storing tritium (T). However, ZrCo is prone to disproportionation reactions during the process of charging and discharging T. Alloying atoms are often added in ZrCo, occupying the Zr or Co site, in order to restrain [...] Read more.
Intermetallic alloy ZrCo is a good material for storing tritium (T). However, ZrCo is prone to disproportionation reactions during the process of charging and discharging T. Alloying atoms are often added in ZrCo, occupying the Zr or Co site, in order to restrain disproportionation reactions. Meanwhile, T often decays into helium (He), and the purity of T seriously decreases once He escapes from ZrCo. Therefore, it is necessary to understand the influence of alloying atoms on the basic stability property of He. In this work, we perform systematical ab initio calculations to study the stability property of He in ZrCoH3 (ZrCo adsorbs the H isotope, forming ZrCoH3). The results suggest that the He atom will undergo displacements of 0.31 and 0.12 Å when it substitutes for Co and Zr, respectively. In contrast, the displacements are very large, at 0.67–1.09 Å, for He replacing H. Then, we introduce more than 20 alloying atoms in ZrCo to replace Co and Zr in order to examine the influence of alloying atoms on the stability of He at H sites. It is found that Ti, V, Cr, Mn, Fe, Zn, Nb, Mo, Tc, Ru, Ta, W, Re, and Os replacing Co can increase the substitution energy of H by the He closest to the alloying atom, whereas only Cr, Mn, Fe, Mo, Tc, Ru, Ta, W, Re, and Os replacing Co can increase the substitution energy of H by the He next closest to the alloying atom. The influence of the alloying atom substituting Zr site on the substitution energies is inconspicuous, and only Nb, Mo, Ru, Ta, and W increase the substitution energies of H by the He closest to the alloying atom. The increase in the substitution energy may suggest that these alloy atoms are conducive to fix the He atom in ZrCo and avoid the reduction in tritium purity. Full article
(This article belongs to the Special Issue Experiment and Calculation Simulation to Study Hydrogen-Helium Effect Mechanism in Materials)
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10 pages, 2689 KiB  
Article
Microstructure Evolution in He-Implanted Si at 600 °C Followed by 1000 °C Annealing
by Zhen Yang, Zhiping Zou, Zeyang Zhang, Yubo Xing and Tao Wang
Materials 2021, 14(17), 5107; https://doi.org/10.3390/ma14175107 - 6 Sep 2021
Cited by 2 | Viewed by 1790
Abstract
Si single crystal was implanted with 230 keV He+ ions to a fluence of 5 × 1016/cm2 at 600 °C. The structural defects in Si implanted with He at 600 °C and then annealed at 1000 °C were investigated [...] Read more.
Si single crystal was implanted with 230 keV He+ ions to a fluence of 5 × 1016/cm2 at 600 °C. The structural defects in Si implanted with He at 600 °C and then annealed at 1000 °C were investigated by transmission electron microscopy (TEM) and high-resolution transmission electron microscopy (HRTEM). The microstructure of an as-implanted sample is provided for comparison. After annealing, rod-like defects were diminished, while tangled dislocations and large dislocation loops appeared. Dislocation lines trapped by cavities were directly observed. The cavities remained stable except for a transition of shape, from octahedron to tetrakaidecahedron. Stacking-fault tetrahedrons were found simultaneously. Cavity growth was independent of dislocations. The evolution of observed lattice defects is discussed. Full article
(This article belongs to the Special Issue Experiment and Calculation Simulation to Study Hydrogen-Helium Effect Mechanism in Materials)
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