A5031183969- Fusion materials and technologies
- Nuclear Materials and Properties
- Nuclear reactor physics and engineering
- Nuclear Physics and Applications
- Magnetic confinement fusion research
- Molten salt chemistry and electrochemical processes
- Hydrogen Storage and Materials
- Muon and positron interactions and applications
- Superconducting Materials and Applications
- Nuclear materials and radiation effects
- Particle accelerators and beam dynamics
- Cold Fusion and Nuclear Reactions
- Fusion and Plasma Physics Studies
- Graphite, nuclear technology, radiation studies
- Chemical Synthesis and Characterization
- Extraction and Separation Processes
- Radioactive element chemistry and processing
- Catalysis for Biomass Conversion
- Metallurgical and Alloy Processes
- Ammonia Synthesis and Nitrogen Reduction
- Biofuel production and bioconversion
- Metal and Thin Film Mechanics
- Sustainable Industrial Ecology
- Advancements in Battery Materials
- Nuclear Engineering Thermal-Hydraulics
Kyoto University
2019-2024
Kyoto Bunkyo University
2020-2024
Advanced Energy (United States)
2019
National Institute for Fusion Science
2013-2018
The Graduate University for Advanced Studies, SOKENDAI
2016-2018
National Institutes of Natural Sciences
2013-2017
Nagoya University of Foreign Studies
2016
The University of Tokyo
2008-2012
The engineering validation and design activity (EVEDA) for the International Fusion Materials Irradiation Facility (IFMIF) is proceeding as one of ITER broader approach activities. In concept IFMIF, two 40 MeV deuteron beams are injected into a liquid Li stream (Li target) flowing at velocity 15 m s −1 . EVEDA test loop (ELTL) aimed validating hydraulic stability target up to 20 under vacuum condition 10 −3 Pa most important issue. Construction ELTL, which largest metal possessing 5.0 3...
A Flinak/LiPb twin-loop Orosh2i-2 was constructed in the Fusion Engineering Research Project of NIFS to establish an engineering basis for "real function" a liquid blanket fusion energy reactors. It with 3 T superconducting magnet, which is strongest world these purposes. In this study, 120 litter Flinak and LiPb were successfully prepared in-situ purified glove-box. Designed flow velocity up 1.5 m/sec achieved both. The magnetic field dependence on pressure drop agreed well theoretical...
Neutron irradiation of a molten salt tritium breeder is planned to evaluate accountancy in the liquid immersion blanket robust (LIBRA) project at MIT. A sealed-tube deuterium-tritium (DT) fusion neutron generator (NG) will be used for irradiation. Hence, NG's characterization necessary accountancy. Specifically, profile, energy, and flux are essential factors analysis experiment. This study aims investigate distribution around NG DT environment. First, neutrons on outer surface were measured...
Abstract We report a neutronics study of blanket mock-up using discharge-type compact fusion neutron source. Deuterium–deuterium neutrons were irradiated to the mock-ups composed tritium breeder and reflector/moderator. The production rate (TPR) per source was measured by single-crystal diamond detector with 6 Li-enriched lithium fluoride film convertor after calibration process. Despite low yield, energetic alpha triton particles via Li(n, t) α capture as well 12 C elastic scattering...
A glow discharge (GD) fusion neutron source that utilizes nuclear reactions of deuterium has been upgraded. The in this device mainly occur by collisions between the charged or neutral particles and hydrogen isotopes trapped at surface electrodes. In addition, it is known metal hydride coating on electrode enhances production rate (NPR). Therefore, elemental distribution, including deuterium, depth direction an essential factor production. However, distribution not experimentally...
The International Fusion Materials Irradiation Facility (IFMIF), presently in the Engineering Validation and Design Activities (EVEDA) phase was started from 2007 under frame of Broader Approach (BA) agreement. In activities, a prototype Li loop with world's highest flow rate 3000 L/min constructed 2010, it succeeded generating 100 mm wide 25 thick free-surface lithium along concave back plate steadily at high-speed 15 m/s 250 °C for 1300 h. demonstration operation needed to develop flowing...
Measurement of thermal and epithermal neutron spatial distribution inside the fusion breeding blanket is essential for evaluating tritium performance. This work aims to establish method measure fluxes in by employing a combination different material foils utilizing differences between various ( <inline-formula xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink"> <tex-math notation="LaTeX">$n$ </tex-math></inline-formula> , notation="LaTeX">$\gamma$ )...