Article
Materials Science, Multidisciplinary
Zhenbo Zhu, Hefei Huang, Ondrej Muransky, Jizhao Liu, Zhiyong Zhu, Yi Huang
Summary: The study investigated the irradiation damage behavior in nano-grained Ni-Mo-Cr alloy irradiated by He ions. Nano-grained GH3535 showed better irradiation swelling resistance than coarse-grained GH3535, but exhibited a more significant increase in hardness under the same irradiation dose, indicating stronger irradiation-induced hardening due to the impeding effect of grain boundaries decorated with He bubbles.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Nuclear Science & Technology
Ke Shi, Wei Zhang, Zhien Ning, Hui Wang, Jiali Liao, Yuanyou Yang, Ning Liu, Jijun Yang
Summary: The study observed that proton and Au-ion irradiation resulted in different types of dislocation structures and voids in F/M steel. Additionally, hardening effects were present in the irradiated F/M steel samples.
NUCLEAR MATERIALS AND ENERGY
(2021)
Article
Materials Science, Multidisciplinary
Aniruddh Das, Eberhard Altstadt, Cornelia Kaden, Garima Kapoor, Shavkat Akhmadaliev, Frank Bergner
Summary: Nanoindentation of ion-irradiated nuclear structural materials and model alloys has been widely studied, but systematic investigations into the effect of self-ion energy are still lacking. In this study, different materials were irradiated with ions of varying energies, and nanoindentation experiments were conducted to explore the effect of ion energy on material properties. Two models were used to explain the experimental results, taking into account microstructural evidence and addressing ion-neutron transferability issues.
FRONTIERS IN MATERIALS
(2022)
Article
Materials Science, Multidisciplinary
Liang Xia, Kai Liu, Yucheng Cao, Chao Jiang
Summary: This study investigates the microstructure information and mechanical behavior of ion-irradiated zirconium alloys through experimental measurements and theoretical analysis. Experimental procedures involve Au3+ irradiation of specific alloys, and transmission electron microscopy analysis reveals the formation of precipitates and their transformation after ion-irradiation. Macroscopic mechanical properties are characterized by nano-indentation tests, revealing significant indentation size effect and irradiation hardening behavior. A mechanistic model is developed to explain the depth-dependent hardness observed in ion-irradiated zirconium alloys.
INTERNATIONAL JOURNAL OF REFRACTORY METALS & HARD MATERIALS
(2024)
Article
Materials Science, Multidisciplinary
Liang Xia, Jianzhong Mao, Ding Chen, Yucheng Cao, Xiazi Xiao, Chao Jiang
Summary: In this work, microstructure observation and thermo-mechanical property characterization of ion-irradiated Zr-0.5Sn-0.5Nb-0.3Fe-0.015Si alloys were investigated. Experimental results showed that the addition of solute elements facilitated the formation of second phase particles and their transformation from crystalline to amorphous state during irradiation. The actual irradiation depth exceeded the predicted value. The influence of irradiation-induced defects on the macroscopic mechanical behaviors of Zr alloys was studied through nano-indentation tests.
JOURNAL OF NUCLEAR MATERIALS
(2022)
Article
Engineering, Mechanical
Jiaqing Shi, Guisen Liu, Kaitao Wu, Ping Yu, Heng Zhu, Guannan Zhao, Yao Shen
Summary: In this study, a comprehensive solution for predicting the neutron irradiation hardening of tungsten is presented. The model is calibrated and validated using compression and indentation experiments, and improved by incorporating more accurate irradiation defect strengthening mechanisms. Results show a good match between the predicted and experimental hardness increases, and discuss the limitations of conventional hardening models.
INTERNATIONAL JOURNAL OF PLASTICITY
(2022)
Article
Materials Science, Multidisciplinary
Arunodaya Bhattacharya, Jean Henry, Brigitte Decamps, Steven J. Zinkle, Estelle Meslin
Summary: Under high temperature conditions, helium significantly modifies the dislocation loop Burgers vector in Fe-Cr alloys, causing certain types of loops to completely disappear and leading to higher loop densities in the alloys.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Materials Science, Multidisciplinary
A. Saikumaran, R. Mythili, P. Magudapathy, C. David
Summary: A novel multi-principal elemental high-entropy alloy, CrFeMoV alloy, was synthesized based on the composition of void swelling resistant ferritic steel. Through experimentation, it was found that the designed CrFeMoV alloy showed better hardening resistance at all doses of irradiation with helium ions compared to P91 ferritic steel.
JOURNAL OF MATERIALS ENGINEERING AND PERFORMANCE
(2021)
Article
Nuclear Science & Technology
G. Kapoor, P. Chekhonin, C. Kaden, K. Vogel, F. Bergner
Summary: Hardening of Fe-9%Cr alloys exposed to irradiation with Fe2+ ions of two different energies is investigated using nanoindentation. The limited penetration depth of the ions causes steep damage gradients in the near-surface volumes of the irradiated samples, resulting in graded microstructures and depth-dependent irradiation hardening. The observed microstructures consist of dislocation loops with band-like distributions and are concluded to be the dominant source of the measured irradiation-induced hardening. Linear superposition is found to be the most appropriate selection under the present conditions for predicting the hardening contributions.
NUCLEAR MATERIALS AND ENERGY
(2022)
Article
Materials Science, Multidisciplinary
Huan Yan, Xiang Liu, Lingfeng He, James Stubbins
Summary: In this experiment, the microstructure evolution and hardening mechanism of Fe-9Cr F/M steel T91 under neutron irradiation in different temperature ranges were studied. The results show significant coarsening of Ni/Si/Mn clusters and fast coalescence of dislocation loops at high temperatures.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Chemistry, Physical
P. P. Cao, H. Wang, J. Y. He, C. Xu, S. H. Jiang, J. L. Du, X. Z. Cao, E. G. Fu, Z. P. Lu
Summary: The evolution of nanosized precipitates in high entropy alloys under irradiation was studied, showing that the precipitates quickly became disordered and dissolved. The presence of nanosized precipitates delayed defect evolution and reduced the sizes of dislocation loops, providing insight into the irradiation resistance of the alloys.
JOURNAL OF ALLOYS AND COMPOUNDS
(2021)
Article
Materials Science, Multidisciplinary
K- Fukumoto, T. Mabuchi, K. Yabuuchi, K. Fujii
Summary: After irradiation with Fe ions, significant irradiation hardening and subsequent recovery were observed in the stainless steel model alloy, mainly attributed to Ni-Si clusters and Frank loops. The dense formation of Ni-Si clusters plays a controlling role in the behavior of irradiation hardening.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Materials Science, Multidisciplinary
Haechan Jo, Sanghun Park, Daegun You, Sooran Kim, Dongwoo Lee
Summary: One of the challenges in fusion reactors is finding plasma facing materials capable of withstanding extreme conditions. Utilizing combinatorial experiments, this study investigates the irradiation damage behaviors of nanostructured tungsten alloys and identifies composition ranges with excellent damage tolerance.
JOURNAL OF NUCLEAR MATERIALS
(2022)
Article
Nuclear Science & Technology
Fan Bai, Wei Zhang, Long Wang, Yongjin Feng, Kaiming Feng, Ning Liu, Jijun Yang
Summary: The corrosion behavior of CLF-1 steel irradiated by 6 MeV Au-ions was studied in a solid tritium breeder of Li4SiO4 at 550℃. The irradiation caused hardening in CLF-1 steel and resulted in the formation of a double corrosion layer on the surface of the samples. The thickness of the corrosion layer increased with the level of irradiation damage, and a newly formed corrosion product of Li2Fe3O4 appeared at the highest damage level.
FUSION ENGINEERING AND DESIGN
(2022)
Article
Materials Science, Multidisciplinary
Pengcheng Zhu, Yajie Zhao, Shradha Agarwal, Jean Henry, Steven J. Zinkle
Summary: Estimations of bulk hardness from nanoindentation can be uncertain due to various factors, but with proper testing methods and corrections for effects like pileup, accurate predictions can be made for different materials. A study on high purity Fe and Fe-Cr alloys showed consistent results under different conditions, with pileup corrections helping to improve the accuracy of bulk hardness measurements.
MATERIALS & DESIGN
(2022)
Article
Chemistry, Physical
Zimo Gao, Hao Yu, Diancheng Geng, Yuchen Liu, Sosuke Kondo, Yasuki Okuno, Ryuta Kasada
Summary: The addition of Zr significantly increases the Vickers hardness of ODS-Cu alloy, with excellent strength mainly attributed to the strengthening effect caused by refined oxide particles. The fine and dense oxide particles in the alloy, along with a slight impact on thermal diffusivity, provide insights for potential thermal aging treatments to restore the diffusivity.
JOURNAL OF ALLOYS AND COMPOUNDS
(2022)
Article
Materials Science, Multidisciplinary
Koichi Sato, Ryuta Kasada, Atsushi Kiyohara, Masashi Hirabaru, Kenichi Nakano, Kiyohiro Yabuuchi, Masahiko Hatakeyama, Qiu Xu
Summary: The effects of hydrogen atoms on the hardness of unirradiated, ion-irradiated, and electron-irradiated polycrystalline tungsten samples were investigated using nanoindentation tests. The study found that the hardness of unirradiated and electron-irradiated tungsten samples did not change upon hydrogen charging, while the hardness of ion-irradiated tungsten samples increased. The hydrogen atoms were mainly trapped at dislocation loops, and the hardening was mainly caused by an increase in the obstacle strength of vacancy clusters containing hydrogen atoms.
JOURNAL OF NUCLEAR MATERIALS
(2022)
Article
Nuclear Science & Technology
Yuyang Zheng, Diancheng Geng, Hao Yu, Sosuke Kondo, Akihiko Kimura, Hideki Yuya, Ryuta Kasada
Summary: This study examined the mechanical properties of irradiated materials using ultra-small testing technologies and found a linear relationship between nanoindentation hardness and Vickers hardness. The size dependence of yield stress in micropillars was minimal at a specific size.
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY
(2022)
Article
Materials Science, Multidisciplinary
Ken-ichi Fukumoto, Kohei Umehara, Kiyohiro Yabuuchi
Summary: A series of in-situ TEM observations were conducted on ion-irradiated stainless steel during tensile deformation. The study revealed that dislocations in the material were pinned and depinned at the defects, and Frank loops and black dots were found to strongly interact with dislocations.
Article
Nuclear Science & Technology
Suguru Nakano, Jae-Hwan Kim, Taehyun Hwang, Ryuta Kasada, Masaru Nakamichi
Summary: A new wet process using microwaves at lower temperatures was proposed to extract beryllium from beryl, reducing the environmental risk and cost compared to the traditional high-temperature processing methods. Chemical reactions between beryl and NaOH at around 200 degrees C were found to play a crucial role in lowering the process temperature. Separation tests successfully separated Al and Si from beryl minerals and recovered beryllium oxide and beryllium hydroxide from the solution.
NUCLEAR MATERIALS AND ENERGY
(2022)
Article
Nuclear Science & Technology
Kouichi Tougou, Maoto Fukui, Ken-ichi Fukumoto, Ryoya Ishigami, Kiyohiro Yabuuchi
Summary: The irradiation hardening factor of cavities with a diameter of 2 nm in tungsten was investigated to be 0.53, with about 11% of the cross-slip behavior attributed to the dynamic interaction between screw dislocations and cavities. The fraction of cross-slip behavior in tungsten was found to be smaller compared to other BCC structure materials.
NUCLEAR MATERIALS AND ENERGY
(2022)
Article
Materials Science, Multidisciplinary
Peng Song, Kiyohiro Yabuuchi, Philippe Spaetig
Summary: FeCrAl(Zr)-ODS ferritic steels were studied to understand their radiation hardening behavior. Irradiation-induced hardening increased with increasing displacement damage, and the addition of Zr reduced the ion-irradiation hardening. The relationship between the plastically deformed zone size and the density of geometrically necessary dislocations was determined.
Article
Materials Science, Multidisciplinary
Diancheng Geng, Hao Yu, Sosuke Kondo, Ryuta Kasada
Summary: This study introduces the concept of Meyer hardness to explain the linear correlation between Vickers hardness and nanoindentation hardness. The real contact area in nanoindentation tests is estimated using a pile-up correction method, improving the accuracy of the test results.
JOURNAL OF MATERIALS SCIENCE
(2022)
Article
Materials Science, Multidisciplinary
Kiyohiro Yabuuchi, Tomoaki Suzudo
Summary: Irradiation defects in reactor materials lead to degradation of mechanical properties. This study focuses on the relationship between dislocations and defects, specifically investigating the interaction between an edge dislocation and different faceted void geometrical combinations in pure iron. The results reveal the differences in obstacle strength and cutting process between spherical voids and faceted voids, with the highest critical shear stress observed at different regions depending on the faceted void configuration type. The cutting process is influenced by the faceted plane, with the {1101 plane of the faceted void requiring the highest amount of energy to cut the atomic binding.
JOURNAL OF NUCLEAR MATERIALS
(2023)
Article
Materials Science, Multidisciplinary
Takuya Yamamoto, Yuan Wu, Kiyohiro Yabuuchi, Jack Haley, Kenta Yoshida, Akihiko Kimura, G. Robert Odette
Summary: The microstructural evolutions of two variants of the F82H 8 wt%Cr tempered martensitic steel under dual ion irradiations have been investigated. The study focuses on the effects of displacements per atom (dpa) and the helium/dpa ratio (He/dpa) on cavity evolution and void swelling. The analysis suggests that local microstructural variations contribute to the observed scatter in the data, and the highest void swelling data provides the most appropriate estimate of swelling for fusion neutron irradiation conditions. The dose dependence of void swelling can be described by an incubation dpa and a post-incubation swelling rate, which both decrease with increasing He/dpa.
JOURNAL OF NUCLEAR MATERIALS
(2023)
Article
Materials Science, Multidisciplinary
Akihiko Kimura, Wei Sang, Wentuo Han, Kiyohiro Yabuuchi, Zongxi Xin, Junhua Luan, Peng Dou
Summary: The age-hardening behavior of oxide dispersion strengthened (ODS) ferritic steels with different Cr and Al contents was studied through Vickers hardness measurement and tensile tests after ageing at 475 degrees C for up to 900 hours. Atom probe tomography (APT) was used to investigate the evolution of nanometer-scale structure and chemistry. The results revealed that the age-hardening mechanism in ODS steels involves alpha-alpha' phase separation and/or the precipitation of (Al, Ti)-enriched f1 phases. The concentration and volume fraction of alpha' phase increased significantly with increasing Cr content, while the chemical compositions and volume fraction of f1 phases remained relatively constant during ageing.
JOURNAL OF NUCLEAR MATERIALS
(2023)
Article
Materials Science, Ceramics
Yuki Jimba, Yasuki Okuno, Sosuke Kondo, Hao Yu, Yasuyuki Ogino, Shuhei Nogami, Ryuta Kasada
Summary: This study demonstrates the successful use of mechanically milled Ti-based sintering aids to improve the density and strength of TiB-TiB2 ceramics under low-temperature sintering conditions. The particle and crystallite sizes of the aids are found to be crucial parameters affecting the sintering behavior.
CERAMICS INTERNATIONAL
(2023)
Review
Materials Science, Multidisciplinary
S. Ukai, K. Sakamoto, S. Ohtsuka, S. Yamashita, A. Kimura
Summary: This paper presents an overview of the development of recrystallized FeCrAl-ODS claddings as an accident-tolerant fuel in Japan. The co-addition of Cr and Al suppresses steam oxidation and inhibits brittle precipitate formation. The incorporation of Zr improves high temperature strength and oxidation resistance. FeCrAl-ODS cladding provides a greater safety margin, high temperature strength, and a higher integral LOCA burst temperature compared to other alloys.
JOURNAL OF NUCLEAR MATERIALS
(2023)
