Search Results - "Ohira, Shigeru"
-
1
Development of a compact real-time process gas analysis system for tritium accountancy for a DEMO fusion reactor by an application of laser Raman spectroscopy
Published in Fusion engineering and design (01-09-2021)“…•A compact real-time gas analysis system for tritium accountancy using laser Raman system for a DEMO is developed.•Preliminary test results of the proto-type…”
Get full text
Journal Article -
2
Radiation safety study for the beam commissioning of IFMIF/EVEDA LIPAc RFQ in Rokkasho
Published in Fusion engineering and design (01-11-2018)“…The construction of the Linear IFMIF Prototype Accelerator (LIPAc) is in progress at Rokkasho, Japan. The important milestone of the project is to commission…”
Get full text
Journal Article -
3
Progress of water cooled ceramic breeder test blanket module system
Published in Fusion engineering and design (01-12-2020)“…A Water-Cooled Ceramic Breeder (WCCB) Test Blanket Module (TBM) System is being developed as one of the most important steps toward DEMO blanket in Japan. As…”
Get full text
Journal Article -
4
Linear IFMIF Prototype Accelerator (LIPAc): Installation activities for Phase-B beam commissioning in Rokkasho
Published in Nuclear materials and energy (01-05-2018)“…•The installation of Linear IFMIF Prototype Accelerator (LIPAc) is progressing.•RFQ, MEBT and beam diagnostics are in line and ready for beam commissioning.•RF…”
Get full text
Journal Article -
5
Operation Scenarios and Requirements for Fuel Processing in Future Fusion Reactor Facilities: Hydrogen Isotope Separation as a Key Process for Fuel Recycle and Safety
Published in Journal of Nuclear Science and Technology (01-04-2006)“…Operability and operation scenario of hydrogen Isotope Separation System (ISS) for ITER and a demo reactor are checked and examined based on the information in…”
Get full text
Journal Article Conference Proceeding -
6
Operation Scenarios and Requirements for Fuel Processing in Future Fusion Reactor Facilities: Hydrogen Isotope Separation as a Key Process for Fuel Recycle and Safety
Published in Journal of nuclear science and technology (01-04-2006)“…Operability and operation scenario of hydrogen Isotope Separation System (ISS) for ITER and a demo reactor are checked and examined based on the information in…”
Get full text
Journal Article -
7
Progress and achievements of the BA activities in Rokkasho
Published in Fusion engineering and design (01-10-2013)“…In Rokkasho Japan, the International Fusion Energy Research Center (IFERC) project and the International Fusion Materials Irradiation Facility/Engineering…”
Get full text
Journal Article -
8
Inhibition of HIV-1 gene expression by retroviral vector-mediated small-guide RNAs that direct specific RNA cleavage by tRNase ZL
Published in Nucleic acids research (01-01-2005)“…The tRNA 3′-processing endoribonuclease (tRNase Z or 3′ tRNase; EC 3.1.26.11) is an essential enzyme that removes the 3′ trailer from pre-tRNA. The long form…”
Get full text
Journal Article -
9
Tritium contamination and decontamination study on materials for ITER remote handling equipment
Published in Fusion engineering and design (01-09-2001)“…Several materials, lenses, dry bearings and cables were exposed to a tritiated moisture environment to study the behavior of tritium contamination on candidate…”
Get full text
Journal Article -
10
Tritium behavior in the Caisson, a simulated fusion reactor room
Published in Fusion engineering and design (01-11-2000)“…In order to confirm tritium confinement ability in the deuterium–tritium (DT) fusion reactor, intentional tritium release experiments have been started in a…”
Get full text
Journal Article Conference Proceeding -
11
Tritium Decontamination from Co-deposited Layer on Tungsten Substrate by Ultra Violet Lamp and Laser
Published in Journal of nuclear science and technology (01-11-2001)“…Tritium decontamination using ultra violet (UV) lamp and laser was performed. Simulated co-deposited layer on tungsten substrate was deposited by C 2 H 2 or C…”
Get full text
Journal Article -
12
Functional Overview of the RF Power System for the LIPAc RFQ
Published in IEEE transactions on plasma science (01-09-2021)“…Design, development, manufacturing, and test activities of the RF power system (RFPS) for Linear IFMIF Prototype Accelerator (LIPAc) were completed in Europe…”
Get full text
Journal Article -
13
Progress of fusion fuel processing system development at the Japan Atomic Energy Research Institute
Published in Fusion engineering and design (01-11-2000)“…The Tritium Process Laboratory (TPL) at the Japan Atomic Energy Research Institute has been working on the development of fuel processing technology for fusion…”
Get full text
Journal Article Conference Proceeding -
14
Beta induced reaction study on T2-CO system
Published in Fusion engineering and design (01-11-2000)Get full text
Conference Proceeding Journal Article -
15
Overview of tritium safety studies in Japan
Published in Fusion engineering and design (01-12-2002)“…Tritium safety is one of the most important R&D subjects for developing International Thermonuclear Experimental Reactor (ITER) and fusion reactor. In Japan,…”
Get full text
Journal Article Conference Proceeding -
16
Beta induced reaction study on T sub(2)-CO system
Published in Fusion engineering and design (01-11-2000)“…To identify the reaction products and process in the reaction of T sub(2)-CO 1:1 mixed system, infrared adsorption spectroscopy was applied. From the results…”
Get full text
Journal Article -
17
Beta induced reaction study on T 2–CO system
Published in Fusion engineering and design (01-11-2000)“…To identify the reaction products and process in the reaction of T 2–CO 1:1 mixed system, infrared adsorption spectroscopy was applied. From the results of…”
Get full text
Journal Article -
18
-
19
Tritium Decontamination from Co-deposited Layer on Tungsten Substrate by Ultra Violet Lamp and Laser
Published in Journal of nuclear science and technology (01-11-2001)“…Tritium decontamination using ultra violet (UV) lamp and laser was performed. Simulated co-deposited layer on tungsten substrate was deposited by C2H2 or C2D2…”
Get full text
Journal Article -
20
Study on decay heat removal of compact ITER
Published in Fusion engineering and design (01-11-2001)“…Since fusion power and neutron fluence of the compact ITER has been reduced, thermal transients due to decay heat of the tokamak components such as in-vessel…”
Get full text
Journal Article Conference Proceeding