Publication

Science and technology research and development in support to ITER and the Broader Approach at CEA

Publications associées (33)

The magnet feeders for the European DEMO fusion reactor: Conceptual design and recent advances

Rainer Wesche, Roberto Guarino, Frédéric Michel

The magnet feeders are part of the critical systems of a fusion reactor since they represent the interface between the in-cryostat components at 4.5 K and the room-temperature cryogenic plant and power supply. The European DEMO tokamak foresees 16 toroidal ...

Lausanne2024

Progress in the development of the ITER baseline scenario in TCV

Olivier Sauter, Stefano Coda, Benoît Labit, Alessandro Pau, Alexander Karpushov, Antoine Pierre Emmanuel Alexis Merle, Oleg Krutkin, Cassandre Ekta Contré, Reinart Andreas J. Coosemans, Stefano Marchioni, Yann Camenen, Matteo Vallar, Filippo Bagnato, Simon Van Mulders

Under the auspices of EUROfusion, the ITER baseline (IBL) scenario has been jointly investigated on AUG and TCV in the past years and this paper reports on the developments on TCV. It is found that the performance of TCV IBL is mainly limited by (neoclassi ...

2024

DTT toroidal field conductor samples test in Sultan: DC and AC characterization

Kamil Sedlák

The superconducting magnet system of the Divertor Tokamak Test (DTT) facility, composed of 18 toroidal field (TF) coils, 6 poloidal field coils and a central solenoid, has been designed and many procurements have been launched. Some manufacturing aspects a ...

Iop Publishing Ltd2024

The MAgnet Design Explorer algorithm (MADE) for LTS, Hybrid or HTS toroidal and poloidal systems of a tokamak with a view to DEMO

The European Roadmap to Fusion Electricity (Federici et al., 2018) [1] details the path to complete within the next three decades the DEMOnstration power plant, DEMO, aiming to a net gain of Energy Q=40. The 2018 DEMO baseline considers a 2 GW tokamak devi ...

ELSEVIER SCIENCE SA2023

The DEMO magnet system - Status and future challenges

Pierluigi Bruzzone, Kamil Sedlák, Davide Uglietti, Federica Demattè, Rainer Wesche, Roberto Guarino, Mithlesh Kumar, Vincenzo D'Auria, Ortensia Dicuonzo, Chiara Frittitta

We present the pre-concept design of the European DEMO Magnet System, which has successfully passed the DEMO plant-level gate review in 2020. The main design input parameters originate from the so-called DEMO 2018 baseline, which was produced using the PRO ...

2022

Runaway dynamics in reactor-scale spherical tokamak disruptions

Understanding generation and mitigation of runaway electrons in disruptions is important for the safe operation of future tokamaks. In this paper we investigate the runaway dynamics in reactor-scale spherical tokamaks, focusing on a compact nominal design ...

CAMBRIDGE UNIV PRESS2022

Advance in the conceptual design of the European DEMO magnet system

Pierluigi Bruzzone, Kamil Sedlák, Davide Uglietti, Boris Stepanov, Rainer Wesche, Roberto Guarino, Mithlesh Kumar, Vincenzo D'Auria, Ortensia Dicuonzo, Chiara Frittitta, Elena Gaio, Alberto Ferro

The European DEMO, i.e. the demonstration fusion power plant designed in the framework of the Roadmap to Fusion Electricity by the EUROfusion Consortium, is approaching the end of the pre-conceptual design phase, to be accomplished with a Gate Review in 20 ...

IOP PUBLISHING LTD2020

Non-linear simulations of neoclassical tearing mode control by externally driven RF current and heating, with application to ITER

Fabien Widmer

Neoclassical tearing modes (NTM) must be controlled or suppressed to prevent a degradation of the energy confinement in tokamak plasmas. This can be done applying RF-current via electron cyclotron current drive and -heating at the rational surface where th ...

2019

In many tokamak and stellarator experiments around the globe that arc investigating energy production via controlled thermonuclear fusion, electron cyclotron heating and current drive (ECH&CD) are used for plasma start-up, heating, non-inductive current dr ...

2019

Realistic multi-machine tokamak profile simulations and numerical ramp-down optimization using the RAPTOR code

Anna Teplukhina

Predictive modelling of plasma profiles is an essential part of ongoing research in tokamak plasmas, required for a successful realization of future fusion reactors. This thesis focuses on upgrading the RAPTOR code to extend the area of its applicability f ...

EPFL2018

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