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Wakai, Eiichi; Noto, Hiroyuki*; Shibayama, Tamaki*; Furuya, Kazuyuki*; Ando, Masami*; Kamada, Takaharu*; Ishida, Taku*; Makimura, Shunsuke*
Materials Characterization, 211, p.113881_1 - 113881_10, 2024/05
Times Cited Count：12 Percentile：80.23(Materials Science, Multidisciplinary)The microstructures and mechanical properties of bcc iron-based high entropy alloy (HEA) Fe-20Mn-15Cr-10V-10Al-2.5C (in at%) without Co and Ni elements have been investigated for applications in fields such as accelerator-target system, nuclear reactors and magnetic motors in aircraft and automobiles. This alloy was normalized at 1150
C for 2 hr and then water quenched, and it was heated at 800C for 10 min and then water quenched. The alloy had a bcc-phase and vanadium carbides with 2-3 
m arranging along grain boundaries, and the Vickers hardness was 520 Hv, harder than pure tungsten. Magnetic domain structure was observed in phase differential contrast method in scanning transmission electron microscope, and the micro-size magnetic domains in grain and sub micro size ones were formed near surface, and it is attractive to the magnetic motor field application. Element distribution in nano scale (20 nm) was observed in matrix, and the presence of crystal lattice disorder in the atomic level region was seen. Very high performance for radiation resistance was confirmed with no irradiation hardening at 300 and 500 C to 1 dpa. It can be speculated that this is due to irradiation-induced nanoscale concentration changes and strain relaxation in the HEA. These properties are very attractive in application of several fields.
Wakai, Eiichi; Noto, Hiroyuki*; Shibayama, Tamaki*; Furuya, Kazuyuki*; Wakui, Takashi; Ando, Masami*; Makimura, Shunsuke*; Ishida, Taku*
Science Talks (Internet), 8, p.100278_1 - 100278_4, 2023/12
High entropy alloys tend to combine high strength with good ductility due to their inherent properties. This material is considered as a promising new material not only for higher-performance future general industrial applications, but also for increasing the durability and range of application of radiation-affected equipment in nuclear and radiation environments, and has been rapidly gaining attention in recent years. In this study, two types of high-entropy alloys (Fe-Mn-V-Cr-Al-C and Fe-Si-W-Cr-V) composed of low-radioactive elements (without Ni and Co) were prepared and their basic properties were evaluated for application as new functional materials to be used under radiation in high-energy accelerator target system components, nuclear reactors, fusion reactors, etc. and their basic properties were evaluated. The two materials under development in this study have unique properties in the following respects. The former is expected to be developed as a basic research for high-power motor materials as a new structural material and magnetic properties sharing the features of high strength and low radiation. On the other hand, the latter is expected to be applied as a new functional material in new engineering fields by mixing tungsten, which has the highest melting point among metallic elements, with vanadium, which has a considerably higher melting point, to raise the melting point of the alloy and to design an alloy with high strength.
Ioka, Ikuo; Shibayama, Tamaki*
Journal of Nuclear Science and Technology, 51(5), p.735 - 736, 2014/02
Times Cited Count：0 Percentile：0.00(Nuclear Science & Technology)The research and development of nuclear materials and fuels is aggressively advanced for the improvement of reliability or performance of nuclear systems, such as LWR, FBR, fusion reactor and so on. Many of outstanding researches are presented by the Journal of Nuclear Science and Technology. The latest activity in nuclear materials and fuels was introduced in this summary by surveying the journal.
Nakamichi, Masaru; Kim, Jae-Hwan; Munakata, Kenzo*; Shibayama, Tamaki*; Miyamoto, Mitsutaka*
Journal of Nuclear Materials, 442(1-3), p.S465 - S471, 2013/11
Times Cited Count：12 Percentile：62.12(Materials Science, Multidisciplinary)Ito, Tatsuya*; Yamauchi, Yuji*; Hino, Tomoaki*; Shibayama, Tamaki*; Nobuta, Yuji*; Ezato, Koichiro; Suzuki, Satoshi; Akiba, Masato
Journal of Nuclear Materials, 417(1-3), p.1147 - 1149, 2011/10
Times Cited Count：14 Percentile：68.12(Materials Science, Multidisciplinary)Shibayama, Tamaki*; Nakamichi, Masaru; Miyamoto, Mitsutaka*; Kuga, Noriyoshi*; Dorn, C. K.*; Knudson, T.*
Purazuma, Kaku Yugo Gakkai-Shi, 87(4), p.259 - 267, 2011/04
no abstracts in English
Yano, Yasuhide; Yamashita, Shinichiro; Otsuka, Satoshi; Kaito, Takeji; Akasaka, Naoaki; Shibayama, Tamaki*; Watanabe, Seiichi*; Takahashi, Heishichiro
Journal of Nuclear Materials, 398(1-3), p.59 - 63, 2010/03
Times Cited Count：14 Percentile：64.21(Materials Science, Multidisciplinary)The in-reactor creep rupture tests of 11Cr-0.5Mo-2W, V, Nb F/M steel were carried out in the temperature range from 823 to 943 K using Materials Open Test Assembly in the Fast Flux Test Facility and tensile and temperature-transient-to-burst specimens were irradiated in the experimental fast reactor JOYO at temperatures between 693 to 1013 K to fast neutron doses ranging from 3.5 to 102 dpa. The results of post irradiation mechanical tests showed that there was no significant degradation in tensile and transient burst strengths even after neutron irradiation below 873 K, but that there was significant degradation in both strengths at neutron irradiation above 903 K. On the other hand, the in-reactor creep rupture times were equal or greater than those of out-reactor creep even after neutron irradiation at all temperatures. This creep rupture behavior was different from that of tensile and transient burst specimens.
Nakamichi, Masaru; Shibayama, Tamaki*; Tatenuma, Katsuyoshi*; Yonehara, Kazuo
Proceedings of 9th IEA International Workshop on Beryllium Technology (BeWS-9), p.40 - 43, 2009/09
Shibayama, Tamaki*; Kishimoto, Hirotatsu*; Koyama, Akira*; Yano, Yasuhide
Materia, 47(12), P. 628, 2008/12
no abstracts in English
Mishima, Yoshinao*; Yoshida, Naoaki*; Kawamura, Hiroshi; Ishida, Kiyohito*; Hatano, Yuji*; Shibayama, Tamaki*; Munakata, Kenzo*; Sato, Yoshiyuki*; Uchida, Munenori*; Tsuchiya, Kunihiko; et al.
Journal of Nuclear Materials, 367-370(2), p.1382 - 1386, 2007/08
Times Cited Count：32 Percentile：86.85(Materials Science, Multidisciplinary)no abstracts in English
Tsuchiya, Kunihiko; Kawamura, Hiroshi; Mishima, Yoshinao*; Yoshida, Naoaki*; Tanaka, Satoru*; Uchida, Munenori*; Ishida, Kiyohito*; Shibayama, Tamaki*; Munakata, Kenzo*; Sato, Yoshiyuki*; et al.
Purazuma, Kaku Yugo Gakkai-Shi, 83(3), p.207 - 214, 2007/03
no abstracts in English
Kawamura, Hiroshi; Tsuchiya, Kunihiko; Mishima, Yoshinao*; Yoshida, Naoaki*; Munakata, Kenzo*; Ishida, Kiyohito*; Hatano, Yuji*; Shibayama, Tamaki*; Sato, Yoshiyuki*; Uchida, Munenori*; et al.
INL/EXT-06-01222, p.1 - 7, 2006/02
no abstracts in English
TiShibayama, Tamaki*; Nakamichi, Masaru*; Uchida, Munenori*; Kawamura, Hiroshi; Kinoshita, Hiroshi*; Kiyanagi, Yoshiaki*; Takahashi, Heishichiro*; Nomura, Naoyuki*
JAERI-Conf 2004-006, p.216 - 219, 2004/03
no abstracts in English
Wakai, Eiichi; Shibayama, Tamaki*; Noto, Hiroyuki*; Wakui, Takashi
no journal, ,
In this study, we fabricated a prototype iron-based high-entropy alloy (Fe-Mn-V-Cr-Al-C) composed of low activation elements (free of Ni and Co) by radio frequency melting method and evaluated its basic properties, aiming to apply it to new functional materials for high-energy accelerator target system components, nuclear reactors and fusion reactors. XRD analysis of this material revealed that it has a BCC crystal structure, in which vanadium carbide (VC) is precipitated. This material was found not only to be magnetic, but also to have a fairly small magnetic domain structure. As for the grain size, relatively small grains (about 20-50 m) were observed despite the homogenization heat treatment at 1150C. With regard to strength properties, the results of Vickers hardness measurements indicated that the alloy was much harder than ordinary iron alloys, slightly exceeding pure tungsten, and elastic wave velocity measurements showed that it was faster than iron-based materials and had a higher elastic modulus than stainless steel.
Wakai, Eiichi; Noto, Hiroyuki*; Shibayama, Tamaki*; Iwamoto, Yosuke; Sato, Koichi*; Yano, Yukihiro*; Yoshikawa, Maya*; Nakagawa, Yuki*; Toyota, Kodai; Onizawa, Takashi
no journal, ,
In this study, we attempted to fabricate Fe-based and W-based Fe-HEA and W-HEA, both of which have been studied extensively in recent years to enhance the durability of equipment used in high-energy beam irradiation environments. For Fe-based HEAs, Fe-Mn-Cr-V-Al-C alloys were melted and casted, and then subjected to homogenization heat treatment (homogenization heat treatment (1150C for 2h)). After homogenization heat treatment, a 3-point bending test was performed at room temperature. The homogenization heat treatment resulted in an increase in ductility in the 3-point bending test and a decrease in elastic modulus based on ultrasonic velocity measurements. XRD measurements of this material after heat treatment (800C for 10 min and Water Quenched) showed that it has a BCC structure and a Vickers hardness that exceeds that of pure W. On the other hand, in the preparation of W-based HEA material (W-Fe-Si-V-Cr alloy), an arc melting method using powder was attempted, and it was found that an almost homogeneous crystallized alloy could be produced.
Wakai, Eiichi; Shibayama, Tamaki*; Noto, Hiroyuki*; Furuya, Kazuyuki*; Iwamoto, Yosuke; Wakui, Takashi; Makimura, Shunsuke*; Ishida, Taku*; Ando, Masami*; Sato, Koichi*; et al.
no journal, ,
In fields such as nuclear power and high-energy accelerator target systems, radiation causes degradation of materials and equipment, so materials with high durability and excellent functionality are expected to be created. High-entropy alloys (HEA) are expected to have high irradiation resistance and often have high strength and good ductility. In recent years, research and development is underway worldwide for various applications. In this study, Fe- and Ti-based and W-based HEAs composed of low activation elements (free of Ni and Co) were fabricated. These materials were subjected to X-ray diffraction, microstructural observation, hardness, magnetism, electrical resistance, STEM (or TEM, SEM) and EDS, ultrasonic measurements, and hot isostatic pressing (HIP). Ion irradiation, pulsed laser irradiation, and pulsed electron beam irradiation were also performed on some of the samples to investigate their response characteristics. These HEAs were much harder than normal alloys, and the magnetic properties and related microstructural analysis of Fe-based HEAs revealed that they have interesting properties such as micro magnetic domain structures. In particular, for Fe- and W-based HEAs, the changes in crystal structure, orientation, and internal microstructure induced by HIP treatment and the accompanying effects of high temperature and pressure had a significant effect on magnetic properties and material strength properties. Furthermore, the irradiation response properties of Fe-based HEAs have been characterized.
Wakai, Eiichi; Noto, Hiroyuki*; Shibayama, Tamaki*; Iwamoto, Yosuke; Ishida, Taku*; Sato, Koichi*; Yabuuchi, Atsushi*; Yoshiie, Toshimasa*; Takahashi, Toshiharu*; Kobayashi, Yasuhiro*; et al.
no journal, ,
In recent years, it has been reported that high-entropy alloys (HEA) have high strength but good ductility, and they are being researched and developed by cutting-edge research institutions around the world with the aim of finding various applications in progress. In this study, we considered several Fe-based, W-based, and Ti-based HEAs, excluding Co and Ni elements, in order to aim for use in high radiation fields and considering low-activation properties. These materials mainly have a bcc crystal structure and were fabricated using a melting method and their material properties were evaluated. As a result, it was found that Fe-based HEA has properties that exceed the hardness of pure W and has excellent irradiation resistance. In addition, a Ti-based HEA that can be subjected to high-temperature forging and high-temperature rolling has been found, and evaluation of the optimal heat treatment temperature is progressing. The hardness of W-based HEA increased through Hot Isostatic Pressing (HIP) treatment, and it was found to have the world's highest hardness among HEA materials.
Wakai, Eiichi; Noto, Hiroyuki*; Makimura, Shunsuke*; Ishida, Taku*; Furuya, Kazuyuki*; Shibayama, Tamaki*
no journal, ,
Recently, high-entropy alloys have been vigorously researched and developed by research institutes around the world because of their higher strength and ductility than conventional materials due to their atomic mixing ratio and composition. In this study, titanium-based high-entropy alloys (HEAs), TiVCrZrTa, TiVZrTaAl, and TiVCrZrW, were melted by the cold crucible surface melting method and subjected to homogenization heat treatment at 1200C for 5 hours. Mechanical property tests and properties of these HEAs were investigated, and it was found that the TiVCrZrTa HEAs have relatively better hot-rollability and hot-forgeability than other titanium-based HEAs. The Vickers hardness of these titanium-based HEAs was also found to be considerably higher than that of normal titanium alloys.
Iwamoto, Yosuke; Wakai, Eiichi; Nakagawa, Yuki*; Shibayama, Tamaki*
no journal, ,
In order to develop a new non-destructive inspection technique to accurately measure defects inside materials in radiation fields such as nuclear power plants, accelerators, and aerospace, we have measured the time evolution of electrical resistivity of copper, aluminum, and niobium metal wires and silicon plates by irradiating a pulsed laser beam (20 Hz) at Hokkaido University. From the obtained increase in electrical resistivity, the number of atomic vacancies and Frenkel pairs (FPs) of interstitial atoms and the dislocation density of the formed FPs were estimated, assuming that the atoms were ejected by the laser due to electronic excitation. From this experiment, it was estimated that for metals, the amount of defects formed inside the material increased with the increase in the irradiation dose. On the other hand, for silicon, the electrical resistivity was found to decrease due to the electronic transition to the valence band caused by laser irradiation.
-Ti alloysWakai, Eiichi; Kano, Sho*; Ishida, Taku*; Makimura, Shunsuke*; Shibayama, Tamaki*; Wakui, Takashi
no journal, ,
In this study, the irradiation behavior and microstructural changes of Ti-15V-3Al-3V-3Sn (abbreviated as Ti-15-3), one of the beta-Ti alloys among the Ti alloys, were investigated by ion irradiation in order to improve the durability performance of equipment used in irradiation environments. depth dependence, but from the present observation, it was found that dislocation loops were not observed up to a region of about 9 dpa. In addition, diffraction pattern analysis was performed to investigate the formation of omega-phase by irradiation, and it was found that the atomic arrangement was disordered due to the formation of nano-sized materials that may be precursors of omega-phase, and that the diffuse scattering streaks became stronger with increasing dpa. On the other hand, irradiation hardening of about 1 GPa was observed in the Ti-64 material under the same conditions, while almost no irradiation hardening was observed in the T-15-3 material, indicating that it has high irradiation resistance.
