A5091047039- Fusion materials and technologies
- Nuclear Materials and Properties
- Hydrogen embrittlement and corrosion behaviors in metals
- Advanced Materials Characterization Techniques
- Corrosion Behavior and Inhibition
- Metal and Thin Film Mechanics
- Advanced materials and composites
- Muon and positron interactions and applications
- Magnesium Alloys: Properties and Applications
- Aluminum Alloy Microstructure Properties
- Powder Metallurgy Techniques and Materials
- Titanium Alloys Microstructure and Properties
- Aluminum Alloys Composites Properties
- Metal Alloys Wear and Properties
- Ion-surface interactions and analysis
- Electrocatalysts for Energy Conversion
- Nuclear Physics and Applications
- Catalysis and Hydrodesulfurization Studies
- High-Temperature Coating Behaviors
- Magnetic confinement fusion research
- Engineering Applied Research
- Extraction and Separation Processes
- Metallurgy and Material Forming
- Anodic Oxide Films and Nanostructures
- High Temperature Alloys and Creep
University of Toyama
2015-2024
Tohoku University
2008-2023
Institute for Materials Research, Tohoku University
2003-2021
Materials Science & Engineering
2019
Japan Atomic Energy Agency
2015
University of Wisconsin–Madison
2013
Kyushu University
1994-2004
The effects of neutron and ion irradiations on deuterium (D) retention in tungsten (W) were investigated. Specimens pure W irradiated with neutrons to 0.3 dpa at around 323 K then exposed high-flux D plasma 473 773 K. concentration significantly increased by irradiation reached 0.8 at% 0.4 Annealing tests for the specimens 20 MeV ions showed that defects which play a dominant role trapping high temperature stable least up 973 K, while density decreased temperatures equal or above 1123 These...
Nanostructured tungsten (W)-based materials offer many advantages for use as plasma facing and components exposed to heavy thermal loads combined with irradiation high-energy neutron low-energy ion. This paper first presents the recent progress in nanostructured toughened, fine grained, recrystallized W materials. Thermal desorption spectrometry apparatus equipped an ion gun has been installed radiation controlled area our Center at Tohoku University systematically investigate effects of...
Nanostructural evolution of Cr (Cr-rich) precipitates in a Cu-0.78%Cr-0.13%Zr alloy has been studied after aging and overaging (reaging) by laser assisted local electrode 3 dimensional atom probe (Laser-LEAP). This material is candidate for the first wall divertor components future fusion reactors. After prime at 460°C, enriched with Zr were observed. Further reaging 600°C caused to grow almost spherical 5 nm (1 h) diameter plate-like ones 20 (4 h), respectively. impurities Si Fe...
Precipitation-hardened Cu–Cr–Zr alloy is proposed as a heat sink material for various components of the ITER owing to its high strength, conductivity, and superior resistance against neutron irradiation. Oxide-dispersion-strengthened copper (ODS-Cu) was selected candidate material. Hydrogen embrittlement Cu–Cr–Zr, Cu–Cr, ODS-Cu (GlidCop® CuAl60) alloys evaluated using slow strain rate technique (SSRT) in 0.1 M sodium sulfate (Na2SO4) solutions under cathodic hydrogen charging or after D2 gas...
Abstract The litter size of mouse strains is determined by the number oocytes naturally ovulated. Many attempts have been made to increase sizes conventional superovulation regimens (e.g., using equine or human gonadotropins, eCG/hCG but had limited success because unexpected decreases in numbers embryos surviving term. Here, we examined whether rat-derived anti-inhibin monoclonal antibodies (AIMAs) could be used for this purpose. When C57BL/6 female mice were treated with an AIMA and mated,...
Defect-sensitive and element-selective measurements on ultrathin chrome, copper, gold layers embedded in aluminium are presented using coincident Doppler broadening spectroscopy (CDBS) with a monoenergetic positron beam. The amounts of positrons implanted the different thicknesses calculated compared experimentally gained fractions annihilating buried layers. A high sensitivity was already reached at an Au layer only 2 nm thickness below 200 Al, which attributed to highly efficient trapping...
A bioactive TiNbSn alloy was anodized in an electrolyte of sodium tartrate containing hydrogen peroxide (H2O2). The photo-induced characteristics the were explored by focusing on its crystallinity and electrochemical conditions. electrolysis curve anodization exhibited a higher voltage substrate than pure Ti substrate. Highly crystallized porous rutile-structured TiO2 formed TiNbSn, whereas relatively low-crystallized glassy anatase-structured Ti. absorption spectra oxide, revealed steep...
Precipitation-hardened Cu-Cr-Zr alloy is proposed as a heat sink material for various components of the ITER (blanket first wall, divertor, electrical straps and others) owing to its high strength, conductivity superior resistance against neutron irradiation. ODS-Cu (Oxide Dispersion Strengthened Copper) also selected candidate material. Corrosion properties alumina-dispersed copper alloys (GlidCop® CuAl15, CuAl25), aevaluated by electrochemical methods in 0.1 M 0.01 sodium sulfate (Na2SO4)...
A three-dimensional atom probe (3DAP) technique was used to observe the solute distribution around screw dislocations in neutron-irradiated modified 316 austenitic stainless steel. Si, Ni, and P were observed get enriched cores of dislocations, while Fe, Cr, Mn, Mo depleted same areas. Si segregated a narrow region core for which, it concluded that trapped initial stage segregation. Other elements some edge features such as kinks and/or jogs formed result trapping. The results suggest...
Duplex stainless steel (DSS) can be used in harsh environments owing to its excellent strength and corrosion resistance. However, the sigma (σ) phase, which reduces resistance, precipitates during manufacturing. To elucidate deterioration mechanism of we prepared three types DSS (F55) with different volume fractions σ phase. Polarization curves were measured investigate characteristics. The rate potential (Ecorr) evaluated using Tafel extrapolation. Owing precipitation Ecorr was low, high,...
Solute/impurity segregation and precipitation at grain boundaries (GBs) in a nuclear reactor pressure vessel (RPV) steel were investigated using laser-assisted atom probe tomography (APT): RPV surveillance test specimens irradiated commercial to neutron doses of 0.83 × 1019 n·cm−2 (low-dose) 5.1 (high-dose), corresponding in-service exposure ∼5 ∼30 years, respectively. The C, P Mo was found on GBs after the low-dose irradiation. Si Mn as well observed high-dose monolayer coverage is...