A5035304310- Fusion materials and technologies
- Fluid Dynamics and Mixing
- Nuclear Materials and Properties
- Nuclear reactor physics and engineering
- Heat Transfer and Boiling Studies
- Fluid Dynamics and Turbulent Flows
- Cyclone Separators and Fluid Dynamics
- Nuclear Engineering Thermal-Hydraulics
- Metallurgical Processes and Thermodynamics
- Particle Dynamics in Fluid Flows
- Magnetic confinement fusion research
- Flow Measurement and Analysis
- Granular flow and fluidized beds
- Superconducting Materials and Applications
- Spacecraft and Cryogenic Technologies
- Heat transfer and supercritical fluids
- Heat Transfer Mechanisms
- Aerosol Filtration and Electrostatic Precipitation
- Fluid Dynamics and Heat Transfer
- Fluid Dynamics and Vibration Analysis
- Nanofluid Flow and Heat Transfer
- Erosion and Abrasive Machining
- High-pressure geophysics and materials
- Engineering Applied Research
- Laser-Plasma Interactions and Diagnostics
Kyoto University
2013-2024
Kyoto Katsura Hospital
2014-2024
Kyushu University
2003-2018
IFMIF, the International Fusion Materials Irradiation Facility, is presently in its engineering validation and design activities (EVEDA) phase under Broader Approach Agreement.
The International Fusion Materials Irradiation Facility (IFMIF), presently in its Engineering Validation and Design Activities (EVEDA) phase under the frame of Broader Approach Agreement between Europe Japan, accomplished summer 2013, on schedule, EDA with release engineering design report IFMIF plant, which is here described. Many improvements from former phases are implemented, particularly a reduction beam losses operational costs thanks to superconducting accelerator concept, re-location...
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...
Gas–liquid two-phase flows are typical in engineering systems involving heat and mass transfers. The cross-sectional geometries sizes of these flow channels vary, exerting a notable impact on the thermofluid behavior. To develop models, it is imperative to obtain local measurements gain insights into their characteristics from measurements. Numerous experimental studies have investigated circular pipes rectangular channels; however, few square been conducted, particularly for regimes beyond...
AbstractAn investigation of MHD effects on Flibe simulant fluid (aqueous potassium hydroxide solution) flows has been conducted under the U.S.-Japan JUPITER-II collaboration program using "FLIHY" pipe flow facility at UCLA. Mean and fluctuating temperature profiles in a conducting wall were measured for low Reynolds number turbulent thermocouples probe constant heat flux condition. It is suggested that are characterized by interaction between turbulence production, suppression due to...
In a lead-lithium (Pb-17Li) liquid metal blanket concept, Pb-17Li eutectic alloy circulates both as breeder and coolant under strong plasma-confining magnetic field, experiencing magneto-hydro-dynamic (MHD) force: Lorentz force. An important aspect of the bilateral US/Japan collaboration on Tritium, Irradiations, Thermofluid for America Nippon (TITAN) is to investigate tritium behavior thermal control in alloy, flow heat transfer characterizations, mitigation MHD effects. The present paper...
Thermohydraulic analysis of postulated accidents will identify system responses to accident scenarios and aid in developing design safety systems strategies prevent or mitigate propagation. This paper reports analyses four a fusion DEMO reactor based on water-cooled ceramic-pebble breeder blanket. The analyzed, which were selected the previous logical analysis, are ex-vessel loss coolant primary cooling system, in-vessel first wall (FW) pipes, blanket modules, vacuum. have identified...
The PHENIX Project is a 6-year U.S./Japan bilateral, multi-institutional collaboration program for the Technological Assessment of Plasma Facing Components DEMO Reactors. goal to address technical feasibility helium-cooled divertor concepts using tungsten as armor material in fusion power reactors. project specifically attempts (1) improve heat transfer modeling systems through experiments including steady-state and pulsed high-heat-load testing, (2) understand thermomechanical properties...
As part of the engineering validation and design activities (EVEDA) phase for international fusion materials irradiation facility IFMIF, major elements a lithium target test were designed, prototyped validated. For facility, EVEDA loop was built at JAEA used to stability (waves long term) flow in target, work out startup procedures, purification analysis. It confirmed by experiments Lifus 6 plant ENEA that corrosion on ferritic martensitic steels is acceptably low. Furthermore, complex...
The present paper aims at improving the modeling of turbulence for upward turbulent bubbly flow through use experimental databases that contain data on small and large vertical ducts. First, role bubble-induced was analyzed, which indicated dominant in duct center relatively high void fraction cases. Therefore, therein mainly focused on, stronger could be induced by bubbles ducts with similar fractions as compared to Next, near wall is discussed understand interaction between wall-induced...
The chemical behaviors of non-metal impurities such as O2, H2, N2, H2O, CO2 and CO in lead (Pb) metal, lead-bismuth (Pb-Bi) alloy lead-lithium (Pb-Li) alloys were experimentally investigated by means temperature programmed desorption mass spectrometer (TPD-MS) analysis. Desorption H2O from the Pb metal Pb-Bi was clearly detected TPD-MS However, Pb-Li much less than that alloy, since these molecules are chemically unstable react with Li alloys. Then, oxygen hydrogen must be dissolved they...