Search Results - "Mitarai, O."
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1
Refueling of field-reversed configuration core via axial plasmoids injection
Published in Nuclear fusion (01-09-2024)“…Abstract This study successfully developed a refueling technique for a field-reversed configuration (FRC) via axial plasmoid injection and demonstrated it on…”
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2
Demonstration of transient CHI startup using a floating biased electrode configuration
Published in Nuclear fusion (01-01-2024)“…Abstract Results from the successful solenoid-free plasma startup using the method of transient coaxial helicity injection (transient CHI) in the QUEST…”
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3
Improvements to the High-Field-Side Transient CHI System on QUEST
Published in Journal of fusion energy (01-12-2022)“…Transient coaxial helicity injection (CHI) is a promising candidate for solenoid-free plasma current start-up in a low-aspect-ratio tokamak in support of…”
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4
Design activities on helical DEMO reactor FFHR-d1
Published in Fusion engineering and design (01-08-2012)“…► Conceptual design studies of the helical DEMO reactor FFHR-d1 have been conducted. ► Design window analyses with core plasma and engineering designs have…”
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5
Particle balance in long duration RF driven plasmas on QUEST
Published in Journal of nuclear materials (01-08-2015)“…Global particle balance in non-inductive long-duration plasma on QUEST has been investigated. Approximately 70% of the fuel hydrogen (H) was retained in the…”
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6
Plasma equilibrium based on EC-driven current profile with toroidal rotation on QUEST
Published in Fusion engineering and design (01-09-2019)“…•Plasma current seems to flow in the open magnetic surface in the outside of the closed magnetic surface in the low-field region.•Considering the toroidal…”
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7
Plasma current sustainment after iron core saturation in the STOR-M tokamak
Published in Fusion engineering and design (01-10-2014)“…•Plasma current can be started up by small iron core without central solenoid.•Iron core removes central solenoid.•Plasma current can be maintained after iron…”
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8
Comparative studies of inner and outer divertor discharges and a fueling study in QUEST
Published in Fusion engineering and design (01-11-2016)“…•Central solenoid has a small flux in QUEST.•Large plasma current is obtained when the position is shifted to the inboard side.•Two types of divertor operation…”
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9
Feedback control of the heating power to access the thermally unstable ignition regime in FFHR helical reactor
Published in Fusion engineering and design (01-10-2013)“…•We discovered feedback control method of heating power in helical reactor.•Thermally unstable high-density ignition regime can be accessed by this…”
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10
Plasma equilibrium based on RF-driven current profile without assuming nested magnetic surfaces on QUEST
Published in Fusion engineering and design (01-11-2017)“…In the present RF-driven (ECCD) steady-state plasma on QUEST, the plasma current seems to flow in the open magnetic surface outside of the closed magnetic…”
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11
Optimization activities on design studies of LHD-type reactor FFHR
Published in Fusion engineering and design (01-12-2008)“…Recent activities on optimizing the base design of the large helical device (LHD)-type helical reactor FFHR (force free helical reactor) are presented. Three…”
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Journal Article Conference Proceeding -
12
Heating by an electron Bernstein wave in a spherical tokamak plasma via mode conversion
Published in Physical review letters (12-05-2006)“…The first successful high power heating of a high dielectric constant spherical tokamak plasma by an electron Bernstein wave (EBW) is reported. An EBW was…”
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13
Development of plasma control system for divertor configuration on QUEST
Published in Fusion engineering and design (01-10-2013)“…A plasma control system to sustain divertor configurations is developed on QUEST (Q-shu university experiment with steady-state spherical tokamak). Magnetic…”
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14
Formation of advanced tokamak plasmas without the use of an ohmic-heating solenoid
Published in Physical review letters (23-01-2004)“…A new operational scenario of advanced tokamak formation was demonstrated in the JT-60U tokamak. This was accomplished by electron cyclotron and lower hybrid…”
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15
Conceptual design activities and key issues on LHD-type reactor FFHR
Published in Fusion engineering and design (01-11-2006)“…An overview of conceptual design activities on the LHD-type helical reactor FFHR is presented, mainly focusing on optimization studies on the reactor size and…”
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Journal Article Conference Proceeding -
16
Eddy current-adjusted plasma shape reconstruction by Cauchy condition surface method on QUEST
Published in Fusion engineering and design (01-10-2011)“…CCS (Cauchy Condition Surface) method is a numerical approach to reproduce plasma shape, which has good precision in conventional tokamaks. In order to apply…”
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Journal Article Conference Proceeding -
17
Aspect ratio dependencies of D– 3He fueled tokamak reactors
Published in Fusion engineering and design (01-11-2006)“…Ignition capability is studied and compared for two types of D– 3He spherical tokamak (ST) and medium aspect ratio tokamak (MT) reactors. The required power…”
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Journal Article Conference Proceeding -
18
Progress of design studies on an LHD-type steady state reactor
Published in Fusion engineering and design (01-12-2008)“…Progress of design studies on a heliotron reactor is reported. Recent experimental achievements in large helical device (LHD) are building up the physical…”
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Journal Article Conference Proceeding -
19
Pellet injection algorithm for the FFHR helical reactor
Published in Fusion engineering and design (01-07-2004)“…Pellet injection algorithm has been proposed for engineering developments in the force free helical reactor (FFHR) based on the zero-dimensional equations. In…”
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20
Carbon tiles as spectral-shifter for long-life liquid blanket in LHD-type reactor FFHR
Published in Fusion engineering and design (01-02-2006)“…In terms of engineering feasibility for long-life Flibe blanket in LHD-type reactor FFHR, the Spectral-shifter and Tritium breeder Blanket (STB) concept is…”
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Journal Article Conference Proceeding