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Scaling of the tokamak near the scrape-off layer H-mode power width and implications for ITER

Nuclear fusion, 2013-09, Vol.53 (9), p.93031

2013

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Inter-ELM power decay length for JET and ASDEX upgrade: measurement and comparison with heuristic drift-based model

Physical review letters, 2011-11, Vol.107 (21), p.215001-215001, Article 215001

2011

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Results on the use of tungsten heavy alloys in the divertor of ASDEX Upgrade

Journal of nuclear materials, 2018-12, Vol.511, p.567-573

2018

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Real time capable infrared thermography for ASDEX Upgrade

Review of scientific instruments, 2015-11, Vol.86 (11)

2015

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Investigation of scrape-off layer and divertor heat transport in ASDEX Upgrade L-mode

Plasma physics and controlled fusion, 2016-05, Vol.58 (5), p.55015-55026

2016

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Divertor studies in nitrogen induced completely detached H-modes in full tungsten ASDEX Upgrade

Nuclear fusion, 2015-03, Vol.55 (3), p.33004

2015

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Correlation between near scrape-off layer power fall-off length and confinement properties in JET operated with carbon and ITER-like wall

Plasma physics and controlled fusion, 2020-08, Vol.62 (8), p.85004

2020

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High-accuracy characterization of the edge radial electric field at ASDEX Upgrade

Nuclear fusion, 2013-05, Vol.53 (5), p.53005

2013

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Scrape-off layer (SOL) power width scaling and correlation between SOL and pedestal gradients across L, I and H-mode plasmas at ASDEX Upgrade

Plasma physics and controlled fusion, 2020-04, Vol.62 (4), p.45015

2020

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Real-time control of NBI fast ions, current-drive and heating properties

Nuclear fusion, 2024-05, Vol.64 (5), p.56002

2024

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Disruption avoidance and investigation of the H-Mode density limit in ASDEX Upgrade

Plasma physics and controlled fusion, 2024-02, Vol.66 (2), p.25004

2024

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Phase relation between rotating phase locked (2, 1) and (3, 1) tearing modes in ASDEX Upgrade

Plasma physics and controlled fusion, 2021-04, Vol.63 (4), p.45018

2021

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Scenario optimization for the tokamak ramp-down phase in RAPTOR: Part A. Analysis and model validation on ASDEX Upgrade

Plasma physics and controlled fusion, 2023-12, Vol.66 (2), p.25006

2023

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DCS satellite: Enhanced plant system integration on ASDEX Upgrade

Fusion engineering and design, 2019-09, Vol.146, p.1737-1740

2019

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Application of AXUV diode detectors at ASDEX Upgrade

Review of scientific instruments, 2014-03, Vol.85 (3)

2014

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Divertor heat load in ASDEX Upgrade L-mode in presence of external magnetic perturbation

Plasma physics and controlled fusion, 2017-09, Vol.59 (9), p.95006

2017

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Analytic 1D approximation of the divertor broadening S in the divertor region for conductive heat transport

Plasma physics and controlled fusion, 2019-08, Vol.61 (8), p.85016

2019

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Dependence of the L-Mode scrape-off layer power fall-off length on the upper triangularity in TCV

Plasma physics and controlled fusion, 2018-04, Vol.60 (4), p.45010

2018

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Investigations on tungsten heavy alloys for use as plasma facing material

Fusion engineering and design, 2017-11, Vol.124, p.450-454

2017

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Experiments and non-linear MHD simulations of hot vertical displacement events in ASDEX-Upgrade

Plasma physics and controlled fusion, 2023-05, Vol.65 (5), p.54003

2023

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Quiescent regions below the X-point in ASDEX upgrade

Plasma physics and controlled fusion, 2021-06, Vol.63 (6), p.65005

2021

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Advances in the physics basis for the European DEMO design

Nuclear fusion, 2015-06, Vol.55 (6), p.63003

2015

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Effect of magnetic perturbations for ELM control on divertor power loads, detachment and consequences of field penetration in ASDEX Upgrade

Plasma physics and controlled fusion, 2019-01, Vol.61 (1), p.14008

2019

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A practical protocol to emulate a reactor scenario on present machines, with application to the ASDEX Upgrade tokamak via predictive modeling

Nuclear fusion, 2023-07, Vol.63 (7), p.74001

2023

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Real-time implementation of the high-fidelity NBI code RABBIT into the discharge control system of ASDEX Upgrade

Nuclear fusion, 2023-06, Vol.63 (6), p.66013

2023

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Scaling of the tokamak near the scrape-off layer H-mode power width and implications for ITER

Inter-ELM power decay length for JET and ASDEX upgrade: measurement and comparison with heuristic drift-based model

Results on the use of tungsten heavy alloys in the divertor of ASDEX Upgrade

Real time capable infrared thermography for ASDEX Upgrade

Investigation of scrape-off layer and divertor heat transport in ASDEX Upgrade L-mode

Divertor studies in nitrogen induced completely detached H-modes in full tungsten ASDEX Upgrade

Correlation between near scrape-off layer power fall-off length and confinement properties in JET operated with carbon and ITER-like wall

High-accuracy characterization of the edge radial electric field at ASDEX Upgrade

Scrape-off layer (SOL) power width scaling and correlation between SOL and pedestal gradients across L, I and H-mode plasmas at ASDEX Upgrade

Real-time control of NBI fast ions, current-drive and heating properties

Disruption avoidance and investigation of the H-Mode density limit in ASDEX Upgrade

Phase relation between rotating phase locked (2, 1) and (3, 1) tearing modes in ASDEX Upgrade

Scenario optimization for the tokamak ramp-down phase in RAPTOR: Part A. Analysis and model validation on ASDEX Upgrade

DCS satellite: Enhanced plant system integration on ASDEX Upgrade

Application of AXUV diode detectors at ASDEX Upgrade

Divertor heat load in ASDEX Upgrade L-mode in presence of external magnetic perturbation

Analytic 1D approximation of the divertor broadening S in the divertor region for conductive heat transport

Dependence of the L-Mode scrape-off layer power fall-off length on the upper triangularity in TCV

Investigations on tungsten heavy alloys for use as plasma facing material

Experiments and non-linear MHD simulations of hot vertical displacement events in ASDEX-Upgrade

Quiescent regions below the X-point in ASDEX upgrade

Advances in the physics basis for the European DEMO design

Effect of magnetic perturbations for ELM control on divertor power loads, detachment and consequences of field penetration in ASDEX Upgrade

A practical protocol to emulate a reactor scenario on present machines, with application to the ASDEX Upgrade tokamak via predictive modeling

Real-time implementation of the high-fidelity NBI code RABBIT into the discharge control system of ASDEX Upgrade

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