Operating a full tungsten actively cooled tokamak: overview of WEST first phase of operation

WEST is an MA class superconducting, actively cooled, full tungsten (W) tokamak, designed to operate in long pulses up to 1000 s. In support of ITER operation and DEMO conceptual activities, key missions of WEST are: (i) qualification of high heat flux plasma-facing components in integrating both technological and physics aspects in relevant heat and particle exhaust conditions, particularly for the tungsten monoblocks foreseen in ITER divertor; (ii) integrated steady-state operation at high confinement, with a focus on power exhaust issues. During the phase 1 of operation (2017–2020), a set of actively cooled ITER-grade plasma facing unit prototypes was integrated into the inertially cooled W coated startup lower divertor. Up to 8.8 MW of RF power has been coupled to the plasma and divertor heat flux of up to 6 MW m−2 were reached. Long pulse operation was started, using the upper actively cooled divertor, with a discharge of about 1 min achieved. This paper gives an overview of the results achieved in phase 1. Perspectives for phase 2, operating with the full capability of the device with the complete ITER-grade actively cooled lower divertor, are also described

First WEST experimental data analysis using machine learning algorithms

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WEST plasma reconstruction chain and IMAS related tools

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Preparations for deuterium tritium experiments on the Tokamak Fusion Test Reactor

The final hardware modifications for tritium operation have been completed for the Tokamak Fusion Test Reactor (TFTR). These activities include preparation of the tritium gas handling system, installation of additional neutron shielding, conversion of the toroidal field coil cooling system from water to a Fluorinet{sup {trademark}} system, modification of the vacuum system to handle tritium, preparation and testing of the neutral beam system for tritium operation and a final deuterium-deuterium (D-D) run to simulate expected deuterium-tritium (D-T) operation. Testing of the tritium system with low concentration tritium has successfully begun. Simulation of trace and high power D-T experiments using D-D have been performed. The physics objectives of D-T operation are production of {approximately} 10 megawatts (MW) of fusion power, evaluation of confinement and heating in deuterium-tritium plasmas, evaluation of {alpha}-particle heating of electrons, and collective effects driven by alpha particles and testing of diagnostics for confined {alpha}-particles. Experimental results and theoretical modeling in support of the D-T experiments are reviewed

The Information Technology tools for remote participation and remote experiment control of WEST

International audienceWEST is a full metallic environment tokamak, with an X-point divertorconfiguration. It is targeted at testing ITER like divertor prototypes made ofactively cooled bulk tungsten units, in tokamak conditions during long pulseoperation. The experimental program is conducted with the participation of the WESTpartners from various institutions around the world. We have implementedseveral IT tools to share data and information with all users. They are used sincethe C1 campaign, two years ago. A brief description of these tools and theperspectives for further developmen

Review of Deuterium-Tritium Results from the Tokamak Fusion Test Reactor

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Improving physical understanding and plasma performances in WEST

WEST is a device specialized for long pulse operation in a tungsten environment. Testbed for ITER divertor technology (actively cooled tungsten mono-blocks)Main goal: develop reactor compatible long pulse scenario

Operational space for Lower Hybrid scenarios in the full tungsten environment of WEST

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