The ITER EC H&CD Upper Launcher: Maintenance concepts

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DIII-D research is addressing critical challenges in preparation for ITER and the next generation of fusion devices through focusing on plasma physics fundamentals that underpin key fusion goals, understanding the interaction of disparate core and boundary ...

The integration of the heating and current drive (HCD) systems in the EU DEMO tokamak must address a number of issues, namely space constraints in the tokamak building, remote handling requirements, breeding blanket penetration, neutron and photon radiatio ...

Performance of tokamak fusion plasmas is heavily linked to the radial heat and particle transport, which is known to be mainly produced by turbulence driven by micro-instabilities. Understanding such processes is thus of key importance for the design and o ...

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 ...

Four EC H&CD (Electron Cyclotron Heating and Current Drive) launchers will be installed into the upper ports #12, #13, #15 and #16 in ITER. Beside plasma heating their main purpose is to counteract plasma instabilities by injecting up to 20 MW of microwave ...

The EUROfusion Consortium established in 2014 and composed by European Fusion Laboratories, and in particular the Power Plant Physics and Technology department aims to develop a conceptual design for the Fusion DEMOnstration Power Plant, DEMO. With respect ...

For the development of a DEMOnstration Fusion Power Plant the design of auxiliary heating systems is a key activity in order to achieve controlled burning plasma. The present heating mix considers electron cyclotron resonance heating (ECRH), neutral beam i ...

In the frame of a collaborative effort between the European GYrotron Consortium (EGYC), the European domestic agency Fusion for Energy (F4E) and the Industrial partner Thales Electron Devices (TED), the first continuous wave (CW) prototype of the EU gyrotr ...

The conductor for the ITER Correction Coils (CC) is manufactured in China and is tested in the SULTAN facility. The third China CC conductor for the qualification SULTAN test sample (CCCN3) was prepared from a 200 m long CC conductor unit length (Phase II) ...

Three design concepts, namely, WP#1, WP#2, and WP#3, for the low-T-c superconductor DEMO toroidal field coil was proposed in 2014. This paper is focused on the thermal-hydraulic analysis of all the designs using simplified models, which includes: 1) hydrau ...

Experiments on TCV are designed to complement the work at large integrated tokamak facilities (such as JET) to provide a stepwise approach to extrapolation to ITER and DEMO in areas where medium-size tokamaks can often exploit their experimental capabiliti ...

Since the signature of the ITER treaty in 2006, a new research programme targeting the emergence of a new generation of neutral beam (NB) system for the future fusion reactor (DEMO Tokamak) has been underway between several laboratories in Europe. The spec ...

The ITER EC H&CD Upper Launcher: Maintenance concepts

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DIII-D research towards establishing the scientific basis for future fusion reactors

Initial port integration concept for EC and NB systems in EU DEMO tokamak

Global Flux-Driven Simulations of Ion Temperature-Gradient and Trapped-Electron Modes Driven Turbulence with an Improved Multithreaded Gyrokinetic PIC Code

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

Status Status of the final design of the EC UPP launcher

DEMO port plug design and integration studies

Conceptual design of the EU DEMO EC-system: main developments and R&D achievements

Status and Experimental Results of the European 1 MW, 170 GHz Industrial CW Prototype Gyrotron for ITER

Conductor Performance of CCCN3, CCCN4 and CCCN5 Samples for ITER CC Coils

Thermal-Hydraulic Analysis of the Low-T-c Superconductor (LTS) Winding Pack Design Concepts for the DEMO Toroidal Field (TF) Coil

Upgrade of the TCV tokamak, first phase: Neutral beam heating system

R&D around a photoneutralizer-based NBI system (Siphore) in view of a DEMO Tokamak steady state fusion reactor