Publications related to Modeling and control of the current density profile in tokamaks and its relation to electron transport

Impact of the new TCV baffled divertor upgrade on pedestal structure and performance

Basil Duval, Patrick Blanchard, Holger Reimerdes, Benoît Labit, Christian Gabriel Theiler, Antoine Pierre Emmanuel Alexis Merle, Umar Sheikh, Davide Galassi

A new set of carbon tiles, neutral beam heating optics and gas baffles were installed on TCV during thebaffled divertor upgrade in early 2019. The installation of the baffles allows a deconvolution of the roles ofmain chamber and divertor neutral pressure ...

2021

Wall conditioning in fusion devices with superconducting coils

Stefano Coda

Wall conditioning is essential in tokamak and stellarator research to achieve plasma performance and reproducibility. This paper presents an overview of recent conditioning results, both from experiments in present devices and modelling, in view of devices ...

IOP PUBLISHING LTD2020

TCV heating and divertor upgrades

Ambrogio Fasoli, Basil Duval, Jean-Marc Moret, Stefano Alberti, Holger Reimerdes, Christian Gabriel Theiler, Alexander Karpushov, Matthieu Toussaint, Marcelo Baquero Ruiz, Dario Vaccaro

The operational range and the reactor relevance of the TCV experiments are being enhanced by two sets of major upgrades. The first includes the installation of neutral beam injection (NBI) and new electron cyclotron (EC) auxiliary heating sources, to reach ...

IOP PUBLISHING LTD2020

Assessment of alternative divertor configurations as an exhaust solution for DEMO

Holger Reimerdes, Roberto Maurizio, Seungkyu Ha, Hartmut Zohm

Plasma exhaust has been identified as a major challenge towards the realisation of magnetic confinement fusion. To mitigate the risk that the single null divertor (SND) with a high radiation fraction in the scrape-of-layer (SOL) adopted for ITER will not e ...

2020

Towards integrated control of tokamak plasmas: physics-based control of neoclassical tearing modes in the TCV tokamak

Mengdi Kong

Neoclassical tearing modes (NTMs), magnetic islands located at rational

q

surfaces, are an important class of resistive magnetohydrodynamics (MHD) instabilities in tokamak plasmas, with

q

the safety factor. NTMs are one of the main constraints of the a ...

EPFL2020

DEMO physics challenges beyond ITER

Olivier Sauter, Emiliano Fable, Hartmut Zohm

For electricity producing tokamak fusion reactors like EU-DEMO, it is prudent to choose a plasma scenario close to the ITER baseline, where the largest amount of experimental evidence is available. Nevertheless, there are some aspects in which ITER and EU- ...

2020

Advances in the physics studies for the JT-60SA tokamak exploitation and research plan

Stefano Coda, Javier García Hernández, Marco Wischmeier, Matteo Vallar, Kenji Tanaka, Aylwin Iantchenko, Samuele Mazzi, Leonardo Pigatto

JT-60SA, the largest tokamak that will operate before ITER, has been designed and built jointly by Japan and Europe, and is due to start operation in 2020. Its main missions are to support ITER exploitation and to contribute to the demonstration fusion rea ...

IOP PUBLISHING LTD2020

High-Power Testing of Guided-Wave Components for the ITER ECH Upper Launcher at the FALCON Test Facility

Timothy Goodman, René Chavan, Matteo Vagnoni

Each of the four ITER electron cyclotron heating (ECH) upper launchers (ULs) features eight transmission lines (TLs) made of guided-wave components used to inject 170-GHz microwave power into the plasma at a level of up to 1.31 MW per line, at the TL diamo ...

IEEE-INST ELECTRICAL ELECTRONICS ENGINEERS INC2020

Code Integration, Data Verification, and Models Validation Using the ITER Integrated Modeling and Analysis System (IMAS) in EUROfusion

Olivier Sauter, Antoine Pierre Emmanuel Alexis Merle, Giovanni Tardini

The ITER Integrated Modelling and Analysis System (IMAS) has been adopted by the EUROfusion Consortium as a platform to facilitate the analysis and verification of data from multiple tokamaks for the integration of physics codes and the validation of physi ...

TAYLOR & FRANCIS INC2020

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

Modeling and control of the current density profile in tokamaks and its relation to electron transport

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Impact of the new TCV baffled divertor upgrade on pedestal structure and performance

Wall conditioning in fusion devices with superconducting coils

TCV heating and divertor upgrades

Assessment of alternative divertor configurations as an exhaust solution for DEMO

Towards integrated control of tokamak plasmas: physics-based control of neoclassical tearing modes in the TCV tokamak

DEMO physics challenges beyond ITER

Advances in the physics studies for the JT-60SA tokamak exploitation and research plan

High-Power Testing of Guided-Wave Components for the ITER ECH Upper Launcher at the FALCON Test Facility

Code Integration, Data Verification, and Models Validation Using the ITER Integrated Modeling and Analysis System (IMAS) in EUROfusion

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

TCV heating and divertor upgrades

DEMO physics challenges beyond ITER

Assessment of alternative divertor configurations as an exhaust solution for DEMO

Impact of the new TCV baffled divertor upgrade on pedestal structure and performance

Wall conditioning in fusion devices with superconducting coils

Towards integrated control of tokamak plasmas: physics-based control of neoclassical tearing modes in the TCV tokamak

Advances in the physics studies for the JT-60SA tokamak exploitation and research plan

Code Integration, Data Verification, and Models Validation Using the ITER Integrated Modeling and Analysis System (IMAS) in EUROfusion

High-Power Testing of Guided-Wave Components for the ITER ECH Upper Launcher at the FALCON Test Facility

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