Publications associées à Effects of ECRH power and safety factor on laser blow-off injected impurity confinement in TCV

Mixed hydrogen-deuterium plasmas on JET ILW

A study of mixed hydrogen-deuterium H-mode plasmas has been carried out in JET-ILW to strengthen the physics basis for extrapolations to JET D-T operation and to support the development of strategies for isotope ratio control in future experiments. Variati ...

2020

Development and optimisation of advanced auxiliary ion heating schemes for 3D fusion plasma devices

Hamish William Patten

The magnetic confinement fusion devices known as the tokamak and the stellarator are progressing towards becoming viable commercial nuclear fusion reactor designs. Both ap- proaches require improvements in the applied heating sources and in the particle an ...

EPFL2019

Pedestal structure and energy confinement studies on TCV

Olivier Sauter, Basil Duval, Patrick Blanchard, Benoît Labit, Christian Gabriel Theiler, Antoine Pierre Emmanuel Alexis Merle, Umar Sheikh, Cedric Kar-Wai Tsui

High external gas injection rates are foreseen for future devices to reduce divertor heat loads and this can influence pedestal stability. Fusion yield has been estimated to vary as strongly as T-e,ped(2) so an understanding of the underlying pedestal phys ...

2019

Stationarity of I-mode operation and I-mode divertor heat fluxes on the ASDEX Upgrade tokamak

Antoine Pierre Emmanuel Alexis Merle, Bernhard Sieglin

Recent I-mode investigations from the ASDEX Upgrade tokamak are reported. It is shown that neutral-beam-injection heated I-modes can be stationary, which is important in terms of extrapolability towards future fusion devices. Furthermore, detailed studies ...

ELSEVIER SCIENCE BV2019

Pedestal Structure and Energy Confinement Studies on TCV

Olivier Sauter, Basil Duval, Patrick Blanchard, Benoît Labit, Christian Gabriel Theiler, Antoine Pierre Emmanuel Alexis Merle, Umar Sheikh, Cedric Kar-Wai Tsui

High external gas injection rates are foreseen for future devices to reduce divertor heat loads and this can influence pedestal stability. Fusion yield has been estimated to vary as strongly as

{T}_{e,{\rm{ped}}}^{2}

so an understanding of the underlying ...

2018

Mitigation of divertor heat loads by strike point sweeping in high power JET discharges

Jonathan Graves

Deliberate periodic movement (sweeping) of the high heat flux divertor strike lines in tokamak plasmas can be used to manage the heat fluxes experienced by exhaust handling plasma facing components, by spreading the heat loads over a larger surface area. S ...

Iop Publishing Ltd2017

Physics and performance of the I-mode regime over an expanded operating space on Alcator C-Mod

Christian Gabriel Theiler, Yu Lin

New results on the I-mode regime of operation on the Alcator C-Mod tokamak are reported. This ELM-free regime features high energy confinement and a steep temperature pedestal, while particle confinement remains at L-mode levels, giving stationary density ...

2017

Hierarchical Model Predictive Control in Fusion Reactors

Stefano Coda, Jean-Marc Moret, Hoang Bao Le

Nuclear fusion still has to pass several milestones on its way to successful energy production, one of them being successful plasma stabilization. The present article presents an innovative control implementation related to plasma control for the generatio ...

Ieee2016

On the non-stiffness of edge transport in L-mode tokamak plasmas

Olivier Sauter, Basil Duval, Stefano Coda, Timothy Goodman, Stephan Brunner, Alexander Karpushov, Antoine Pierre Emmanuel Alexis Merle, Yann Camenen, Roland Behn, Doohyun Kim, Gabriele Merlo, Lucia Isabel Federspiel, Donghyun Kim

Transport analyses using first-principle turbulence codes and 11/2-D transport codes usually study radial transport properties between the tokamak plasma magnetic axis and a normalized minor radius around 0.8. In this region, heat transport shows significa ...

Amer Inst Physics2014

Infrared Thermography of Divertor ELM Heat Loads on TCV

János Márki

Edge Localised Mode (ELM)-induced heat loads, in particular divertor heat loads present one of the main challenges in adopting nuclear fusion as an industrial-scale energy source. At present, the type-I ELMy plasma regime is chosen as the most suitable ope ...

EPFL2012

Effects of ECRH power and safety factor on laser blow-off injected impurity confinement in TCV

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Mixed hydrogen-deuterium plasmas on JET ILW

Development and optimisation of advanced auxiliary ion heating schemes for 3D fusion plasma devices

Pedestal structure and energy confinement studies on TCV

Stationarity of I-mode operation and I-mode divertor heat fluxes on the ASDEX Upgrade tokamak

Pedestal Structure and Energy Confinement Studies on TCV

Mitigation of divertor heat loads by strike point sweeping in high power JET discharges

Physics and performance of the I-mode regime over an expanded operating space on Alcator C-Mod

Hierarchical Model Predictive Control in Fusion Reactors

On the non-stiffness of edge transport in L-mode tokamak plasmas

Infrared Thermography of Divertor ELM Heat Loads on TCV

Hierarchical Model Predictive Control in Fusion Reactors

Physics and performance of the I-mode regime over an expanded operating space on Alcator C-Mod

Pedestal Structure and Energy Confinement Studies on TCV

Development and optimisation of advanced auxiliary ion heating schemes for 3D fusion plasma devices

Stationarity of I-mode operation and I-mode divertor heat fluxes on the ASDEX Upgrade tokamak

Infrared Thermography of Divertor ELM Heat Loads on TCV

Pedestal structure and energy confinement studies on TCV

Mixed hydrogen-deuterium plasmas on JET ILW

Mitigation of divertor heat loads by strike point sweeping in high power JET discharges

On the non-stiffness of edge transport in L-mode tokamak plasmas