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Liquid surfaces for fusion plasma facing components—A critical review. Part I: Physics and PSI

Nuclear materials and energy, 2016-12, Vol.9 (C), p.6-21

2016

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Strongly temperature-dependent, anomalous secondary electron emission of liquid lithium surfaces exposed to a plasma

Nuclear materials and energy, 2021-06, Vol.27, p.100966, Article 100966

2021

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Role of nitrogen inventory and ion enhanced N-H recombination in the ammonia formation on tungsten walls. A DC glow discharge study

Vacuum, 2018-05, Vol.151, p.66-72

2018

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A lithium laser-ablation based time-of-flight (LILA-TOF) diagnostic for measuring plasma edge ion temperature and toroidal plasma rotation

Plasma physics and controlled fusion, 2021-12, Vol.63 (12), p.125037

2021

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Temperature dependence of liquid lithium film formation and deuterium retention on hot W samples studied by LID-QMS. Implications for future fusion reactors

Nuclear fusion, 2018-02, Vol.58 (4), p.46003

2018

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Analysis of LiSn alloy at several depths using LIBS

Fusion engineering and design, 2017-04, Vol.117, p.175-179

2017

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Electron-induced secondary electron emission coefficient of lithium, tungsten and stainless steel surfaces exposed to low-pressure plasmas

Journal of nuclear materials, 2014-09, Vol.452 (1-3), p.37-40

2014

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Reactor plasma facing component designs based on liquid metal concepts supported in porous systems

Nuclear fusion, 2017-01, Vol.57 (1), p.16029

2017

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Cold plasma studies on the influence of surface microstructured thickness in the secondary electron emission from tungsten coatings

Nuclear materials and energy, 2023-03, Vol.34, p.101388, Article 101388

2023

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Comparative study of different Sn wetted W CPSs exposed to NBI fluxes in the OLMAT facility

Fusion engineering and design, 2023-05, Vol.190, p.113711, Article 113711

2023

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Wall conditioning in fusion devices with superconducting coils

Plasma physics and controlled fusion, 2020-03, Vol.62 (3), p.34002

2020

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Laboratory experiments of uptake and release of hydrogen isotopes in liquid lithium

Journal of nuclear materials, 2015-08, Vol.463, p.1173-1176

2015

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Physics and Technology Research for Liquid-Metal Divertor Development, Focused on a Tin-Capillary Porous System Solution, at the OLMAT High Heat-Flux Facility

Journal of fusion energy, 2023-09, Vol.42 (2), p.45, Article 45

2023

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Self-consistent determination of the ion thermalization rate at the plasma boundary of TJ-II by the supersonic He beam diagnostic

Nuclear fusion, 2015-01, Vol.55 (1), p.13020

2015

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Design and Testing of Advanced Liquid Metal Targets for DEMO Divertor: The OLMAT Project

Journal of fusion energy, 2020-12, Vol.39 (6), p.411-420

2020

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Sheared flows and transition to improved confinement regime in the TJ-II stellarator

Plasma physics and controlled fusion, 2009-12, Vol.51 (12), p.124015

2009

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Behavior of liquid Li-Sn alloy as plasma facing material on ISTTOK

Fusion engineering and design, 2017-04, Vol.117, p.208-211

2017

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Initial Exploration of High-Field Pulsed Stellarator Approach to Ignition Experiments

Journal of fusion energy, 2018-12, Vol.37 (6), p.275-290

2018

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Tritium inventory control during ITER operation under carbon plasma-facing components by nitrogen-based plasma chemistry: a review

Plasma sources science & technology, 2013-04, Vol.22 (3), p.33001

Tabarés, F L

2013

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Hydrogen retention studies on lithiated tungsten exposed to glow discharge plasmas under varying lithiation environments using Thermal Desorption Spectroscopy and mass spectrometry

Fusion engineering and design, 2017-04, Vol.117, p.212-216

2017

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First thermal fatigue studies of tungsten armor for DEMO and ITER at the OLMAT High Heat Flux facility

Nuclear materials and energy, 2024-03, Vol.38, p.101615, Article 101615

2024

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Studies of lithium deposition and D retention on tungsten samples exposed to Li-seeded plasmas in PISCES-A

Plasma physics and controlled fusion, 2017-04, Vol.59 (4), p.44006

2017

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Comparative studies of H absorption/desorption kinetics and evaporation of liquid lithium in different porous systems and free surfaces

Fusion engineering and design, 2017-04, Vol.117, p.217-221

2017

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Exposure of liquid lithium confined in a capillary structure to high plasma fluxes in PILOT-PSI—Influence of temperature on D retention

Fusion engineering and design, 2017-04, Vol.117, p.222-225

2017

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Comparative studies of liquid metals for an alternative divertor target in a fusion reactor

Physica scripta, 2017-12, Vol.T170 (1), p.14054

2017

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Liquid surfaces for fusion plasma facing components—A critical review. Part I: Physics and PSI

Strongly temperature-dependent, anomalous secondary electron emission of liquid lithium surfaces exposed to a plasma

Role of nitrogen inventory and ion enhanced N-H recombination in the ammonia formation on tungsten walls. A DC glow discharge study

A lithium laser-ablation based time-of-flight (LILA-TOF) diagnostic for measuring plasma edge ion temperature and toroidal plasma rotation

Temperature dependence of liquid lithium film formation and deuterium retention on hot W samples studied by LID-QMS. Implications for future fusion reactors

Analysis of LiSn alloy at several depths using LIBS

Electron-induced secondary electron emission coefficient of lithium, tungsten and stainless steel surfaces exposed to low-pressure plasmas

Reactor plasma facing component designs based on liquid metal concepts supported in porous systems

Cold plasma studies on the influence of surface microstructured thickness in the secondary electron emission from tungsten coatings

Comparative study of different Sn wetted W CPSs exposed to NBI fluxes in the OLMAT facility

Wall conditioning in fusion devices with superconducting coils

Laboratory experiments of uptake and release of hydrogen isotopes in liquid lithium

Physics and Technology Research for Liquid-Metal Divertor Development, Focused on a Tin-Capillary Porous System Solution, at the OLMAT High Heat-Flux Facility

Self-consistent determination of the ion thermalization rate at the plasma boundary of TJ-II by the supersonic He beam diagnostic

Design and Testing of Advanced Liquid Metal Targets for DEMO Divertor: The OLMAT Project

Sheared flows and transition to improved confinement regime in the TJ-II stellarator

Behavior of liquid Li-Sn alloy as plasma facing material on ISTTOK

Initial Exploration of High-Field Pulsed Stellarator Approach to Ignition Experiments

Tritium inventory control during ITER operation under carbon plasma-facing components by nitrogen-based plasma chemistry: a review

Hydrogen retention studies on lithiated tungsten exposed to glow discharge plasmas under varying lithiation environments using Thermal Desorption Spectroscopy and mass spectrometry

First thermal fatigue studies of tungsten armor for DEMO and ITER at the OLMAT High Heat Flux facility

Studies of lithium deposition and D retention on tungsten samples exposed to Li-seeded plasmas in PISCES-A

Comparative studies of H absorption/desorption kinetics and evaporation of liquid lithium in different porous systems and free surfaces

Exposure of liquid lithium confined in a capillary structure to high plasma fluxes in PILOT-PSI—Influence of temperature on D retention

Comparative studies of liquid metals for an alternative divertor target in a fusion reactor

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