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Observation of a reduced-turbulence regime with boron powder injection in a stellarator

Nature physics, 2022-03, Vol.18 (3), p.350-356

2022

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Full‐torus impurity transport simulation for optimizing plasma discharge operation using a multi‐species impurity powder dropper in the large helical device

Contributions to plasma physics (1988), 2020-06, Vol.60 (5-6), p.n/a

2020

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Effects of surface modifications on deuterium retention in F82H and EUROFER exposed to low-energy deuterium plasmas

Fusion engineering and design, 2016-11, Vol.112, p.236-239

2016

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A reduced-turbulence regime in the Large Helical Device upon injection of low-Z materials powders

Nuclear fusion, 2023-07, Vol.63 (7), p.76001

2023

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Plasma wall interaction in long-pulse helium discharge in LHD – Microscopic modification of the wall surface and its impact on particle balance and impurity generation

Journal of nuclear materials, 2015-08, Vol.463, p.91-98

2015

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An overview of tritium retention in dust particles from the JET-ILW divertor

Physica scripta, 2022-02, Vol.97 (2), p.24008

2022

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Effects of surface conditions on the plasma-driven permeation behavior through a ferritic steel alloy observed in VEHICLE-1 and QUEST

Journal of nuclear materials, 2015-08, Vol.463, p.1066-1070

2015

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Measurement of tritium in tungsten deposition layer by imaging plate technique after exposure to gaseous tritium

Fusion engineering and design, 2017-11, Vol.124, p.257-261

2017

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Investigation of carbon dust accumulation in the JT-60U tokamak vacuum vessel

Journal of nuclear materials, 2013-07, Vol.438, p.S659-S663

2013

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First impurity powder injection experiments in LHD

Nuclear materials and energy, 2020-12, Vol.25 (C), p.100842, Article 100842

2020

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Modification of Surfaces of Reduced-Activation Ferritic–Martensitic Steels upon Irradiation by Pulsed Deuterium Plasma with Parameters Typical for Peripheral Plasma Disruption

Surface investigation, x-ray, synchrotron and neutron techniques, 2022-02, Vol.16 (1), p.23-32

2022

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Determination of retained tritium from ILW dust particles in JET

Nuclear materials and energy, 2020-01, Vol.22, p.100673, Article 100673

2020

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Micro/nano structural analysis of mixed-material deposition layer formed on the first walls of large helical device

Journal of nuclear materials, 2011-10, Vol.417 (1-3), p.668-672

2011

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Hydrogen Plasma-Driven Permeation through a Reduced Activation Ferritic Steel Alloy F82H

Fusion science and technology, 2013-05, Vol.63 (1T), p.361-363

2013

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Global distribution of tritium in JET with the ITER-like wall

Nuclear materials and energy, 2021-03, Vol.26, p.100930, Article 100930

2021

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Effects of modified surfaces produced at plasma-facing surface on hydrogen release behavior in the LHD

Nuclear materials and energy, 2017-08, Vol.12, p.483-487

2017

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Hydrogen concentration of co-deposited carbon film produced in the vicinity of LHD divertor tiles

Journal of nuclear materials, 2013-07, Vol.438, p.S1040-S1043

2013

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Bolometric imaging of detached plasmas in LHD

Journal of nuclear materials, 2011-08, Vol.415 (1), p.S1147-S1150

2011

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Recent progress in understanding the behavior of dust in fusion devices

Plasma physics and controlled fusion, 2008-12, Vol.50 (12), p.124054

2008

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Trapping and depth profile of tritium in surface layers of metallic materials

Journal of nuclear materials, 2011-10, Vol.417 (1-3), p.900-903

2011

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Hydrogen permeation and recombination in Ni membrane placed on spherical tokamak QUEST

Journal of nuclear materials, 2011-08, Vol.415 (1), p.S692-S695

2011

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Evaluation of radiation damages on the first-wall surface in LHD exposed to charge-exchanged helium particles

Journal of nuclear materials, 2009-04, Vol.386, p.173-176

2009

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Deuterium retention in deposited W layer exposed to EAST deuterium plasma

Nuclear materials and energy, 2017-08, Vol.12, p.617-621

2017

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Measurement of Dust Quantity and Distribution Collected from JT-60U

Fusion science and technology, 2011-11, Vol.60 (4), p.1548-1551

2011

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Recent researches on dust in EAST and HT-7 tokamaks

Journal of nuclear materials, 2011-08, Vol.415 (1), p.S1094-S1097

2011

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Observation of a reduced-turbulence regime with boron powder injection in a stellarator

Full‐torus impurity transport simulation for optimizing plasma discharge operation using a multi‐species impurity powder dropper in the large helical device

Effects of surface modifications on deuterium retention in F82H and EUROFER exposed to low-energy deuterium plasmas

A reduced-turbulence regime in the Large Helical Device upon injection of low-Z materials powders

Plasma wall interaction in long-pulse helium discharge in LHD – Microscopic modification of the wall surface and its impact on particle balance and impurity generation

An overview of tritium retention in dust particles from the JET-ILW divertor

Effects of surface conditions on the plasma-driven permeation behavior through a ferritic steel alloy observed in VEHICLE-1 and QUEST

Measurement of tritium in tungsten deposition layer by imaging plate technique after exposure to gaseous tritium

Investigation of carbon dust accumulation in the JT-60U tokamak vacuum vessel

First impurity powder injection experiments in LHD

Modification of Surfaces of Reduced-Activation Ferritic–Martensitic Steels upon Irradiation by Pulsed Deuterium Plasma with Parameters Typical for Peripheral Plasma Disruption

Determination of retained tritium from ILW dust particles in JET

Micro/nano structural analysis of mixed-material deposition layer formed on the first walls of large helical device

Hydrogen Plasma-Driven Permeation through a Reduced Activation Ferritic Steel Alloy F82H

Global distribution of tritium in JET with the ITER-like wall

Effects of modified surfaces produced at plasma-facing surface on hydrogen release behavior in the LHD

Hydrogen concentration of co-deposited carbon film produced in the vicinity of LHD divertor tiles

Bolometric imaging of detached plasmas in LHD

Recent progress in understanding the behavior of dust in fusion devices

Trapping and depth profile of tritium in surface layers of metallic materials

Hydrogen permeation and recombination in Ni membrane placed on spherical tokamak QUEST

Evaluation of radiation damages on the first-wall surface in LHD exposed to charge-exchanged helium particles

Deuterium retention in deposited W layer exposed to EAST deuterium plasma

Measurement of Dust Quantity and Distribution Collected from JT-60U

Recent researches on dust in EAST and HT-7 tokamaks

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