A5019549328- Fusion materials and technologies
- Nuclear Materials and Properties
- Advanced materials and composites
- Metal and Thin Film Mechanics
- Nuclear materials and radiation effects
- Microstructure and Mechanical Properties of Steels
- Magnetic confinement fusion research
- Microstructure and mechanical properties
- Nuclear reactor physics and engineering
- Advanced Materials Characterization Techniques
- Radiation Detection and Scintillator Technologies
- Electronic Packaging and Soldering Technologies
- Nuclear Physics and Applications
- Intermetallics and Advanced Alloy Properties
- Superconducting Materials and Applications
- Remote Sensing and Land Use
- Engineering Applied Research
- Twentieth Century Scientific Developments
- Engineering Technology and Methodologies
- Silicon and Solar Cell Technologies
- Muon and positron interactions and applications
- Material Properties and Applications
- Atmospheric chemistry and aerosols
- Thin-Film Transistor Technologies
- Electromagnetic Launch and Propulsion Technology
National Institutes for Quantum Science and Technology
2018-2022
Tohoku University
2011-2020
Fusion Academy
2018
Japan External Trade Organization
2015
Japan Advanced Institute of Science and Technology
2007
Denka (Japan)
1997-2002
Mitsui (Japan)
1993
Kyushu University
1966
The aim of this work is to investigate the influence neutron irradiation condition, especially temperature, on hardening and microstructure development in irradiated tungsten-rhenium (W-Re) alloys. Neutron irradiations were carried out JOYO at range 400 750°C, up 1.54 dpa. Micro Vickers hardness tests micro structural observations using a TEM performed. Irradiation W-Re alloys 538°C clearly larger than those other temperatures. Fine voids fine needle- or plate-like precipitates observed pure...
Tungsten (W) is a candidate for the plasma facing component material of fusion reactors. During reactor operation, not only displacement damage but also transmutation elements such as rhenium (Re) and osmium (Os) are produced in W by neutron irradiation. To understand irradiation response reactor, effects on hardening, microstructure development electric resistivity pure W–Re–Os alloys studied using fission In low-dpa region (<0.4 dpa), hardening was suppressed Re addition, significant...
We aimed to clarify the behavior of change in grain structure and hardness hot-rolled pure W its alloys plates developed for various properties by holding at high temperature long short durations absence irradiation. The isothermal annealing was performed 1100 °C 10–3115 h. isochronous 1 h a range 2300 °C. After heat treatment, observed using electron backscatter diffraction (EBSD) Vickers measured plane. Pure did not recrystallize treatment duration °C, while recrystallization progressed...
The effects of the material fabrication process and rhenium (Re) content on irradiation-induced changes in microstructure hardness pure tungsten (W) WRe alloys were investigated.Neutron irradiation W (Re concentration 326%) was carried out experimental fast reactor JOYO.The conditions 0.44 displacement per atom (dpa) at 531°C 0.47 dpa 583°C for alloys, respectively.After irradiation, microstructural observations using a transmission electron microscope (TEM) Vickers microhardness tests...
The irradiation hardening and microstructures of pure W – 3%Re for up to 5.0 dpa by self-ion were investigated in this work. ion was conducted using 18 MeV W6+ at 500 800 °C. A focused beam followed electro-polishing used make thin foil specimens transmission electron microscope observations. Dislocation loops observed all the irradiated samples. Voids except W–3%Re 0.2 dpa. hardness measured nanoindentation. saturated 1.0 W. In case 3%Re, showed a peak correlation between microstructure...
Neutron irradiation to W induces defects acting as traps against hydrogen isotopes and transmutation elements such Re Os. To investigate synergetic effects on radiation-induced Re, deuterium (D) retention in W–5% samples were examined after with 6.4 MeV Fe ions at 523–1273 K followed by exposure D2 gas 673 K. The value of D was lower than that orders magnitude the high temperatures (≥1073 K), while no significant addition observed 523 Irradiation 20 room temperature plasma 443–743 also...
The United States and Japan have collaborated on fusion materials research in a series of agreements reaching back to 1981. PHENIX collaboration is the latest U.S.-Japan project which spans 2013 2019 has goal assessing technical feasibility tungsten-based, helium-cooled plasma-facing component concepts for demonstration power reactor (DEMO). Task 2 within focused evaluating neutron irradiation effects tungsten. For tungsten, transmutation Re Os at least as important determining its...
The effects of K-bubble dispersion and 3 wt.% Re addition on the tensile properties their anisotropy in W were investigated this work. K-doped W-3%Re showed ∼45 ∼65% higher strengths than pure W, respectively. ultimate strength its temperature dependence anisotropy. However, 3% anisotropic not clearly observed. better deformation abilities W. under non-irradiation conditions used Since irradiation hardening is suppressed by adding Re, expected to be more advantageous as a plasma facing...
The effects of helium (He) on mechanical properties hot-rolled pure W were investigated using a high-energy He-implantation technique and post-implantation tensile tests. After the He implantation, specimens heat treated at 1100 °C for 100 h in order to recrystallize W. tests conducted vacuum 400 700 °C. annealed showed almost same hardness as-received unimplanted specimens. Tensile He-implanted after annealing indicated trend as those under these experimental conditions. Dimples formed...