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Virtual-reality visualization of loss points of 1 MeV tritons in the Large Helical Device, LHD

Journal of visualization, 2022-04, Vol.25 (2), p.281-292

2022

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Tritium removal from the LHD first-wall by the hydrogen plasma discharge

Fusion engineering and design, 2020-10, Vol.159, p.111879, Article 111879

2020

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Subcooled Boiling Heat Transfer for Turbulent Flow of Water in a Short Vertical Tube

Journal of heat transfer, 2010-01, Vol.132 (1), p.011501 (11 )-011501 (11 )

2010

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Exposure of tungsten heavy alloys at high thermal loads in LHD

Nuclear materials and energy, 2024-03, Vol.38, p.101585, Article 101585

2024

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Temperature impact on the micro structure of tungsten exposed to He irradiation in LHD

Journal of nuclear materials, 2017-02, Vol.484, p.24-29

2017

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Application of High-Frequency Ultrasonic Test to the Non-Destructive Inspection of W-Cu Bonded Interface

Plasma and Fusion Research, 2022/03/30, Vol.17, pp.2405013-2405013

2022

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The Effect of the Grain Size of Divertor’s Cooling Pipe on the Capability of High-Frequency Ultrasonic Tests to Evaluate the Quality of the Bond between Divertor’s Cooling Pipe and Armor

Plasma and Fusion Research, 2023/08/10, Vol.18, pp.2405068-2405068

2023

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Helium and hydrogen interaction in tungsten simultaneously irradiated by He+-H2+ at high temperature

International journal of hydrogen energy, 2020-03, Vol.45 (16), p.9959-9968

2020

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Comparison of Hydrogen Isotope Retention in Divertor Tiles of JET with the ITER-Like Wall Following Campaigns in 2011-2012 and 2015-2016

Fusion science and technology, 2020-05, Vol.76 (4), p.439-445

2020

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Tritium Balance in Large Helical Device during and after the First Deuterium Plasma Experiment Campaign

Plasma and Fusion Research, 2020/08/19, Vol.15, pp.1405062-1405062

2020

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Influence of boiling initiation surface superheat on subcooled water flow boiling critical heat flux in a SUS304 circular tube at high liquid Reynolds number

International journal of heat and mass transfer, 2016-07, Vol.98, p.299-312

2016

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Directional Material Probe for Deposition Layer Studies

Plasma and Fusion Research, 2013/08/15, Vol.8, pp.1202110-1202110

MASUZAKI, Suguru

2013

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Correlation of the Orthogonal Basis of the Core Plasma Distribution to the Divertor Footprint Distribution in LHD

Plasma and fusion research, 2023-03, Vol.18, p.2402021-2402021

2023

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EUV/VUV Spectroscopy for the Study of Carbon Impurity Transport in Hydrogen and Deuterium Plasmas in the Edge Stochastic Magnetic Field Layer of Large Helical Device

Plasma, 2023-06, Vol.6 (2), p.308-321

2023

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Co-deposited layers on gap surfaces of bulk tungsten divertor tiles in JET ITER-like wall: Directional effects and nanostructures

Nuclear materials and energy, 2024-06, Vol.39, p.101678, Article 101678

2024

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Mechanism of critical heat flux during flow boiling of subcooled water in a circular tube at high liquid Reynolds number

Experimental thermal and fluid science, 2016-01, Vol.70, p.255-269

2016

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Critical heat fluxes of subcooled water flow boiling in a short vertical tube at high liquid Reynolds number

Nuclear engineering and design, 2010-10, Vol.240 (10), p.3145-3157

2010

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Simulation of Impurity Transport and Deposition in the Closed Helical Divertor in the Large Helical Device

Plasma and Fusion Research, 2021/02/10, Vol.16, pp.2403004-2403004

2021

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Spatial Profiles of NeVI-NeX Emission in ECR-Heated Discharges of the Large Helical Device with Divertor Detachment Induced by RMP Application and Ne Impurity Seeding

Plasma and Fusion Research, 2022/04/22, Vol.17, pp.2402022-2402022

2022

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Observation of Arc Trails with Significant Damage due to Glow Discharge Wall Conditioning in the Large Helical Device

Plasma and Fusion Research, 2021/04/21, Vol.16, pp.1202061-1202061

2021

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Prediction of Radiative Collapse in Large Helical Device Using Feature Extraction by Exhaustive Search

Journal of fusion energy, 2020-12, Vol.39 (6), p.500-511

2020

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ACT2: a High Heat Flux Test Facility Using Electron Beam for Fusion Application

Plasma and Fusion Research, 2016/06/10, Vol.11, pp.2405089-2405089

2016

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Divertor Detachment with Multi-Species Impurity Seeding in LHD

Plasma and Fusion Research, 2020/07/15, Vol.15, pp.1402051-1402051

2020

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EUV and VUV Spectra of NeIII-NeX Line Emissions Observed in the Impurity Gas-Puffing Experiments of the Large Helical Device

Plasma and Fusion Research, 2021/02/10, Vol.16, pp.2402006-2402006

2021

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Data-Driven Control for Radiative Collapse Avoidance in Large Helical Device

Plasma and Fusion Research, 2022/03/30, Vol.17, pp.2402042-2402042

2022

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Virtual-reality visualization of loss points of 1 MeV tritons in the Large Helical Device, LHD

Tritium removal from the LHD first-wall by the hydrogen plasma discharge

Subcooled Boiling Heat Transfer for Turbulent Flow of Water in a Short Vertical Tube

Exposure of tungsten heavy alloys at high thermal loads in LHD

Temperature impact on the micro structure of tungsten exposed to He irradiation in LHD

Application of High-Frequency Ultrasonic Test to the Non-Destructive Inspection of W-Cu Bonded Interface

The Effect of the Grain Size of Divertor’s Cooling Pipe on the Capability of High-Frequency Ultrasonic Tests to Evaluate the Quality of the Bond between Divertor’s Cooling Pipe and Armor

Helium and hydrogen interaction in tungsten simultaneously irradiated by He+-H2+ at high temperature

Comparison of Hydrogen Isotope Retention in Divertor Tiles of JET with the ITER-Like Wall Following Campaigns in 2011-2012 and 2015-2016

Tritium Balance in Large Helical Device during and after the First Deuterium Plasma Experiment Campaign

Influence of boiling initiation surface superheat on subcooled water flow boiling critical heat flux in a SUS304 circular tube at high liquid Reynolds number

Directional Material Probe for Deposition Layer Studies

Correlation of the Orthogonal Basis of the Core Plasma Distribution to the Divertor Footprint Distribution in LHD

EUV/VUV Spectroscopy for the Study of Carbon Impurity Transport in Hydrogen and Deuterium Plasmas in the Edge Stochastic Magnetic Field Layer of Large Helical Device

Co-deposited layers on gap surfaces of bulk tungsten divertor tiles in JET ITER-like wall: Directional effects and nanostructures

Mechanism of critical heat flux during flow boiling of subcooled water in a circular tube at high liquid Reynolds number

Critical heat fluxes of subcooled water flow boiling in a short vertical tube at high liquid Reynolds number

Simulation of Impurity Transport and Deposition in the Closed Helical Divertor in the Large Helical Device

Spatial Profiles of NeVI-NeX Emission in ECR-Heated Discharges of the Large Helical Device with Divertor Detachment Induced by RMP Application and Ne Impurity Seeding

Observation of Arc Trails with Significant Damage due to Glow Discharge Wall Conditioning in the Large Helical Device

Prediction of Radiative Collapse in Large Helical Device Using Feature Extraction by Exhaustive Search

ACT2: a High Heat Flux Test Facility Using Electron Beam for Fusion Application

Divertor Detachment with Multi-Species Impurity Seeding in LHD

EUV and VUV Spectra of NeIII-NeX Line Emissions Observed in the Impurity Gas-Puffing Experiments of the Large Helical Device

Data-Driven Control for Radiative Collapse Avoidance in Large Helical Device

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