On the road to ITER NBIs: SPIDER improvement after first operation and MITICA construction progress

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2021
Article

Résumé

To reach fusion conditions and control the plasma configuration in ITER, the next step in tokamak fusion research, two neutral beam injectors (NBIs) will supply 16.5 MW each, by neutralizing accelerated negative hydrogen or deuterium ions. The requirements of ITER NBIs (40A/1 MeV D-ions for

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On the road to ITER NBIs: SPIDER improvement after first operation and MITICA construction progress

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Full-discharge simulation and optimization with the RAPTOR code, from present tokamaks to ITER and DEMO

Design and Development of a Diagnostic System for a Non-Intercepting Direct Measure of the SPIDER Ion Source Beamlet Current

Full-discharge simulation and optimization with the RAPTOR code, from present tokamaks to ITER and DEMO

An experimental and computational study of tokamak plasma turbulence

Design and Development of a Diagnostic System for a Non-Intercepting Direct Measure of the SPIDER Ion Source Beamlet Current