A5004401428- Particle accelerators and beam dynamics
- Fusion materials and technologies
- Superconducting Materials and Applications
- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
- Nuclear Physics and Applications
- Muon and positron interactions and applications
- Particle Accelerators and Free-Electron Lasers
- Graphite, nuclear technology, radiation studies
- Magnetic confinement fusion research
- Molten salt chemistry and electrochemical processes
- Microstructure and Mechanical Properties of Steels
- Ion-surface interactions and analysis
- Ammonia Synthesis and Nitrogen Reduction
- Toxin Mechanisms and Immunotoxins
- Fungal Biology and Applications
- Radiation Therapy and Dosimetry
- Welding Techniques and Residual Stresses
- Microwave-Assisted Synthesis and Applications
- Laser-Plasma Interactions and Diagnostics
- Spacecraft and Cryogenic Technologies
- Plant-derived Lignans Synthesis and Bioactivity
- Advanced Welding Techniques Analysis
National Institutes for Quantum Science and Technology
2021-2024
The Graduate University for Advanced Studies, SOKENDAI
2008-2019
IHI Corporation (Japan)
2017
Advanced Science Research Center
1981
An accelerator-based neutron source using d-Li reactions is one of the most promising sources for fusion material irradiation facilities such as IFMIF, where 40 MeV deuterons bombard a liquid lithium target. The yield estimation including angular spectra important issues in design facilities. Recently, JAEA released deuteron nuclear data JENDL/DEU-2020 ACE format file Monte Carlo codes MCNP, and Frag-Data PHITS code. We carry out benchmark calculations by with Frag-Data, MCNP JENDL/DEU-2020,...
Release behaviors of tritium from molten FLiNaBe (LiF-NaF-BeF2) have been examined in a series low flux neutron irradiation experiments with an AmBe source at the OKTAVIAN facility Osaka University. Tritium released is swept by He and Ar gases, recovered water bubblers. The recovery rate 300 cm3 was 58.0 mBq/h steady state, it close to production calculated MCNP6 code. values overall mass transfer coefficients for release were those FLiNaK (LiF-NaF-KF) 773 K. influence diffusivity solubility...
In complement to the development activities for fusion reactors (JT-60SA & ITER), Fusion Energy contributes R&D material characterisation facilities. Within Broader Approach agreement, different actors from Europe Japan collaborate develop and assemble in LIPAC, a technical demonstrator of D+ accelerator that will be used produce neutron by nuclear stripping reaction on liquid Li target. 2024, LIPAC is getting ready installation SRF cryomodule conclude its construction. Started March...
The validation of the Linear IFMIF Prototype Accelerator (LIPAc) is being conducted in Rokkasho Fusion Institute QST, Aomori, Japan. beam commissioning novel LIPAc RFQ has been progressing significantly, and acceleration world highest current deuteron 125 mA to 5 MeV (1 ms, 1 Hz pulsed beam) was achieved for 1st time July 2019. This study devoted evaluating amount loss during high phase by measuring neutron produced interaction with accelerator components so as verify design. foil activation...
The use of the isotopic exchange between tritium produced in molten salts and hydrogen molecules a sweep gas has been proposed as way recovering self-cooled salt liquid blanket system [1-3]. In present study, rate coefficients for FLiNaK (LiF-NaF-KF) have evaluated series low flux neutron irradiation experiments with an AmBe source at OKTAVIAN facility Osaka University Japan. Approximately 300 cm3 were irradiated 773 K Inconel 600 crucible, released from free surface swept by pure He or...
With the current practice in steel making and welding process control, thick large structural components fabricated from widely used materials such as SA-738 Grade B have good material properties sufficient enough to meet increasing demand of avoiding a amount Post Weld Heat Treatment (PWHT) applications at both shop site. The original rule ASME Boiler Pressure Vessel Code (the Code), however, allows exemption mandatory PWHT for by limiting applicable thickness equal or less than 1 3/4 in....
Ablation of a solid hydrogen pellet in hot plasmas Large Helical Device (LHD) has been studied. A position sensitive detector (PSD) diagnostics newly installed to measure the trajectory ablating pellets. 2-D enables measurement with high time (1 MHz) and spatial resolutions (80 μm). 3-D can be described by combination images information initial direction velocity. deflection neutral beam injection (NBI) heated LHD observed. Means improving accuracy this system are also discussed.