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Demonstration of Super-X divertor exhaust control for transient heat load management in compact fusion reactors
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Plasma heat load in the toroidal gaps of the ITER-like plasma facing units in WEST tokamak
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Divertor shaping with neutral baffling as a solution to the tokamak power exhaust challenge
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Thermal and statistical analysis of the high-Z tungsten-based UFOs observed during the first deuterium high fluence campaign of the WEST tokamak
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Evolution and cleaning of the deposit layers on the lower divertor of WEST fully equipped with ITER grade components
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WEST full tungsten operation with an ITER grade divertor
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Overview of the EUROfusion Tokamak Exploitation programme in support of ITER and DEMO
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COMPASS Upgrade: a high-field tokamak for ITER- and DEMO-relevant research
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Calorimetry measurement for energy balance and energy distribution in WEST for L-mode plasmas
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Experimental characterization of leading edge cracking on bulk tungsten divertor components during 2017–2019 WEST operation
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Identification of a double decay length ($\lambda^t_q$) heat flux deposition shape with embedded thermal measurement and neural network
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Overview of the EUROfusion Tokamak Exploitation programme in support of ITER and DEMO
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Surface temperature measurement from infrared synthetic diagnostic in preparation for ITER operations
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Studies on EU-DEMO 3D coils requirements and conceptual design for error field correction and plasma control
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Testing of ITER-grade plasma facing units in the WEST tokamak: Progress in understanding heat loading and damage mechanisms
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Conceptual design of Fiber Bragg Grating temperature sensors for heat load measurements in COMPASS-U plasma-facing components
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Front face shaping of the inner wall tiles in the COMPASS Upgrade tokamak
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Infrared detection of tungsten cracking on actively cooled ITER-like component during high power experiment in WEST
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Current quench and vessel currents characterisation at the COMPASS tokamak
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Embedded-probes diagnostics for the COMPASS upgrade tokamak: a concept
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Integrated design strategy for EU-DEMO first wall protection from plasma transients
Francesco Maviglia
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Integrated design strategy for EU-DEMO first wall protection from plasma transients Fusion Engineering and Design 177 (2022) 113067
Francesco Maviglia
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Overview of the COMPASS results
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Sustained W-melting experiments on actively cooled ITER-like Plasma Facing Unit in WEST
Yann Corre
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Inverse Radiation Problem with Infrared Images to Monitor Plasma-Facing Components Temperature in Metallic Fusion Devices
Charly Talatizi
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Fusion Engineering and Design, 2020
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First heat flux estimation in the lower divertor of WEST with embedded thermal measurements
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Article dans une revue
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Simplified heat load modeling for design of DEMO discrete limiter
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Article dans une revue
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Steady and transient pyrolysis of thick clear PMMA slabs
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Article dans une revue
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Taking Accurate Account of Radiative Heat Transfer for the Simulation of Core Reflooding
Jonathan Gérardin
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Pierre Ruyer
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Article dans une revue
hal-01432137
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Optical and radiative properties of clear \PMMA\ samples exposed to a radiant heat flux
Pascal Boulet
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Article dans une revue
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Radiative transfer during the reflooding step of a LOCA
Jonathan Gerardin
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Pierre Ruyer
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Article dans une revue
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P1 approximation, MDA and IDA for the simulation of radiative transfer in a 3D geometry for an absorbing scattering medium
J. Gerardin
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P. Ruyer
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Article dans une revue
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hal-02907264
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