A5021176501- Fusion materials and technologies
- Nuclear Materials and Properties
- Nuclear reactor physics and engineering
- Magnetic confinement fusion research
- Nuclear Physics and Applications
- Superconducting Materials and Applications
- Nuclear materials and radiation effects
- Particle accelerators and beam dynamics
- Semiconductor materials and devices
- Ion-surface interactions and analysis
- Metal and Thin Film Mechanics
- Plasma Diagnostics and Applications
- Molten salt chemistry and electrochemical processes
- Metallurgical Processes and Thermodynamics
- Hydrogen embrittlement and corrosion behaviors in metals
- Radiation Detection and Scintillator Technologies
- Graphite, nuclear technology, radiation studies
- Luminescence Properties of Advanced Materials
- Advanced materials and composites
- Advanced ceramic materials synthesis
- Muon and positron interactions and applications
- Nuclear Engineering Thermal-Hydraulics
- X-ray Spectroscopy and Fluorescence Analysis
- Radiation Effects in Electronics
- High-Temperature Coating Behaviors
National Institute for Fusion Science
2015-2024
National Institutes of Natural Sciences
2006-2024
Nippon Electric Glass (Japan)
2021
The Graduate University for Advanced Studies, SOKENDAI
2010-2020
Nippon Soken (Japan)
2019
Tokyo Institute of Technology
2016
Tokai University
2016
Suzuki (Japan)
2016
University of Wisconsin–Madison
2013
RIKEN
2012
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...
Yttrium oxide coatings were fabricated on reduced activation ferritic/martensitic steels by metal organic decomposition with a dip-coating technique, and their deuterium permeation behaviors investigated. The microstructure of the varied heat-treatment temperature: amorphous at 670 ºC (amorphous coating) crystallized 700 (crystallized coating). Deuterium flux coating was lower than uncoated steel factor 5 500 ºC, while that around 100 400‒550 ºC. fluxes both drastically decreased during...
The Fusion Engineering Research Project (FERP) at the National Institute for Science (NIFS) is conducting conceptual design activities LHD-type helical fusion reactor FFHR-d1A.This paper newly defines two options, "basic" and "challenging."Conservative technologies, including those that will be demonstrated in ITER, are chosen basic option which coils made of continuously wound cable-in-conduit superconductors Nb3Sn strands, divertor composed water-cooled tungsten monoblocks, blanket ceramic...
New design approaches are proposed for the LHD-type heliotron D–T demo-reactor FFHR2 to solve key engineering issues of blanket space limitation and replacement difficulty. A major radius over 14 m is selected permit a blanket-shield thickness about 1 reduce neutron wall loading toroidal field, while achieving an acceptable cost electricity. Two sets optimization successfully carried out. One magnetic hoop force on helical coil support structures by adjustment winding pitch parameter...
The electrical conductivity of the α-Al2O3 layer formed on FeCrAl alloy APMT (Fe-21Cr-5Al-3Mo) in air atmosphere at 1273 K and 1373 was measured a temperature range between room 1073 K. Low clarified measurement range. ZrO2 Zr metal 873 also measured. Numerical simulation performed with three-dimensional thermo-fluid code to clarify reduction magnetohydrodynamic (MHD) pressure drop insulating layers liquid blankets magnetic confinement fusion reactors. MHD is significantly reduced when four...
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...
Conceptual design activity for the LHD-type helical DEMO reactor FFHR-d1 has been conducted at National Institute Fusion Science under Engineering Research Project since FY2010. In first step of conceptual process, window analysis was using system code HELIOSCOPE by “Design Integration Task Group”. On basis a parametric scan with core plasma based on DPE (Direct Profile Extrapolation) method, point having major radius 15.6 m and averaged magnetic field strength coil winding center 4.7 T...