Search Results - "Utoh, Hiroyasu"
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Metallographic and Bending Strain Property Analysis of reinforced Nb3Sn strand candidates for Japanese DEMO
Published in IEEE transactions on applied superconductivity (01-08-2023)“…The influence of a large electromagnetic force on the conductor of a demonstration power plant (DEMO) reactor magnet is a crucial issue. The present study…”
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2
Overview of the DEMO conceptual design activity in Japan
Published in Fusion engineering and design (01-11-2018)“…The requirements for Japanese DEMO are to demonstrate (1) steady and stable electrical power generation, (2) plant availability on a level relevant for…”
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3
Shutdown dose-rate assessment during the replacement of in-vessel components for a fusion DEMO reactor
Published in Fusion engineering and design (01-11-2017)“…•Shutdown dose rate was analyzed to consider a maintenance progress for DEMO by using MCNP-5 and DCHAIN-SP2001.•The dose rate of pipe cutting and re-welding…”
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Technological assessment between vertical and horizontal remote maintenance schemes for DEMO reactor
Published in Fusion engineering and design (01-11-2017)“…•Preliminary assessment for two options of remote maintenance is carried out to establish a feasible maintenance scheme on the DEMO design.•Analysis on the…”
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Safety research on fusion DEMO in Japan: Toward development of safety strategy of a water-cooled DEMO
Published in Fusion engineering and design (01-11-2016)“…•This paper reports the current status of a safety research on water-cooled fusion DEMO in Japan.•We report analyses of two transients: (i) complete loss of…”
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6
Simplification of blanket system for SlimCS fusion DEMO reactor
Published in Fusion engineering and design (01-10-2011)“…Simplification of blanket system is necessary for a fusion DEMO reactor. Although the conceptual design of a tritium-breeding blanket for SlimCS has been…”
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Comparative evaluation of remote maintenance schemes for fusion DEMO reactor
Published in Fusion engineering and design (01-10-2015)“…•Various remote maintenance schemes for DEMO were comparatively assessed based on requirements for DEMO remote maintenance.•The banana shape segment transport…”
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Evaluation of remote maintenance schemes by plasma equilibrium analysis in Tokamak DEMO reactor
Published in Fusion engineering and design (01-11-2014)“…•The remote maintenance schemes in DEMO reactor were evaluated by the plasma equilibrium analysis.•Horizontal sector transport maintenance scheme requires the…”
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Conceptual study of vertical sector transport maintenance for DEMO fusion reactor
Published in Fusion engineering and design (01-08-2012)“…The maintenance scheme is a critical issue for DEMO design, and requires high availability of the reactor. The SlimCS, designed in JAEA, adopts the horizontal…”
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10
Analysis of plasma position control for DEMO reactor
Published in Fusion engineering and design (01-11-2016)“…•Plasma position control for DEMO reactor has been investigated using numerical code.•Stabilization effect of conductors and active feedback control are…”
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Design concept of conducting shell and in-vessel components suitable for plasma vertical stability and remote maintenance scheme in DEMO reactor
Published in Fusion engineering and design (01-02-2016)“…•Conceptual design of in-vessel component including conducting shell has been investigated.•The conducting shell design for plasma vertical stability was…”
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12
Application of inter-linked superconducting coils for central solenoid and advanced divertor configuration of DEMO
Published in Fusion engineering and design (01-10-2014)“…•To determine the engineering feasibility of inter-linked superconducting CS and PF coil, we designed IL-CS and PF coil.•Use of the IL-PF coil enables to…”
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13
Waste management strategy focused on maintenance, storage and recycling
Published in Fusion engineering and design (01-08-2012)“…► Decay heat for each 1/12-sector is as high as 5MW just after the shutdown and 0.3MW one month later. ► For the maintenance, a CSS is proposed to remove the…”
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14
Characterization of Japan's DEMO Candidate Reinforced Nb3Sn Wires Under Crossover Contact Stress
Published in IEEE transactions on applied superconductivity (01-08-2024)“…The size of Japan's demonstration power plant (JA DEMO) reactor is planned to be approximately 1.4 times larger than that of ITER magnet. Mechanical behavior…”
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15
Characterization of Japan's DEMO Candidate Reinforced Nb 3 Sn Wires Under Crossover Contact Stress
Published in IEEE transactions on applied superconductivity (01-08-2024)Get full text
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16
Advantages of Cu-Nb Reinforced Nb }Sn Strands in Large Multi-Stage Stranded Cables With Low-Void Fraction
Published in IEEE transactions on applied superconductivity (01-08-2024)“…A large multi-stage stranded cable structure with Nb<inline-formula><tex-math notation="LaTeX">_{\text{3}}</tex-math></inline-formula>Sn strands twisted at a…”
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Conceptual design of coolant circuits and thermal stress analysis for JA-DEMO divertor
Published in Fusion engineering and design (01-09-2024)“…•JA-DEMO divertor concept with double-coolant circuits of 200°C and 290°C pressurized waters was developed.•Plasma Facing Unit support design for the coolant…”
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Design study of superconducting coil system for JA DEMO
Published in Fusion engineering and design (01-05-2024)“…•The design study of options for cost rationalization and the R&D required for larger coil sizes on JA DEMO is being carried out.•Using "Hybrid R-shape"…”
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Conceptual design of poloidal horseshoe limiter layout for JA DEMO
Published in Fusion engineering and design (01-02-2024)“…•The design flow for the poloidal horseshoe limiter in JA DEMO is rearranged.•The poloidal horseshoe limiter layout was designed according to the flat-top…”
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20
Metallographic and Bending Strain Property Analysis of Reinforced Nb 3 Sn Strand Candidates for Japanese DEMO
Published in IEEE transactions on applied superconductivity (01-08-2023)Get full text
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