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Plasma cleaning of ITER first mirrors

Publications associées (66)

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Assessment of Neutron Production in Neutral Beam Injector of TCV Tokamak

Alexander Karpushov

Neutral beam (NB) injector for the TCV tokamak has been designed to produce a deuterium beam with energy 30 keV, equivalent current up to 50 A, and pulse duration 2 s. The injector operation is accompanied by generation of fast neutrons produced in deuteri ...

Amer Inst Physics2016

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

Neutron yield studies in JET H-modes

Henri Weisen

The measured D-D neutron rate of NBI heated JET baseline and hybrid H-modes in Deuterium is found to be between approximately 50% and 100% of the neutron rate expected from the TRANSP code, depending on plasma parameters. A number of candidate explanations ...

2016

Plasma cleaning of beryllium coated mirrors

Cleaning systems of metallic first mirrors are needed in more than 20 optical diagnostic systems from ITER to avoid reflectivity losses. Currently, plasma sputtering is considered as one of the most promising techniques to remove deposits coming from the m ...

Iop Publishing Ltd2016

Superconductivity and fusion energy-the inseparable companions

Pierluigi Bruzzone

Although superconductivity will never produce energy by itself, it plays an important role in energy-related applications both because of its saving potential (e.g., power transmission lines and generators), and its role as an enabling technology (e.g., fo ...

Iop Publishing Ltd2015

Novel aspects of plasma control in ITER

Olivier Sauter, Federico Alberto Alfredo Felici, Jonathan Bryan Lister, Sun Hee Kim

ITER plasma control design solutions and performance requirements are strongly driven by its nuclear mission, aggressive commissioning constraints, and limited number of operational discharges. In addition, high plasma energy content, heat fluxes, neutron ...

Amer Inst Physics2015

20 years of research on the Alcator C-Mod tokamak

Basil Duval, Christian Gabriel Theiler, Yu Lin

The object of this review is to summarize the achievements of research on the Alcator C-Mod tokamak [Hutchinson et al., Phys. Plasmas 1, 1511 (1994) and Marmar, Fusion Sci. Technol. 51, 261 (2007)] and to place that research in the context of the quest for ...

Amer Inst Physics2014

Superconductivity and fusion energy—the inseparable companions

Pierluigi Bruzzone

2014

Materials R&D for a timely DEMO: Key findings and recommendations of the EU Roadmap Materials Assessment Group

Minh Quang Tran

The findings of the EU Fusion Programme's 'Materials Assessment Group' (MAG), assessing readiness of Structural, Plasma Facing (PF) and High Heat Flux (HHF) materials for DEMO, are discussed. These are incorporated into the EU Fusion Power Roadmap [1] , wi ...

Elsevier Science Sa2014

Funnelling of rf current via a plasmoid through a grid hole in an rf capacitive plasma reactor

Christoph Hollenstein, Alan Howling, Michaël Chesaux

The boundaries of capacitively coupled radio-frequency (rf) plasma reactors generally include at least one grounded metal grid or perforated plate for purposes of gas flow or diagnostic access. When increasing the rf power, an intense localized plasma (a p ...

Iop Publishing Ltd2013