Title
Operating a full tungsten actively cooled tokamak: Overview of WEST first phase of operation
Date Issued
01 April 2022
Access level
open access
Resource Type
review
Author(s)
Bucalossi J.
Achard J.
Agullo O.
Alarcon T.
Allegretti L.
Ancher H.
Antar G.
Antusch S.
Anzallo V.
Arnas C.
Arranger D.
Artaud J.F.
Aumeunier M.H.
Baek S.G.
Bai X.
Balbin J.
Balorin C.
Barbui T.
Barbuti A.
Barlerin J.
Basiuk V.
Batal T.
Baulaigue O.
Bec A.
Bécoulet M.
Benoit E.
Benard E.
Benard J.M.
Bertelli N.
Bertrand E.
Beyer P.
Bielecki J.
Bienvenu P.
Bisson R.
Bobkov V.
Bodner G.
Bottereau C.
Bouchand C.
Bouquey F.
Bourdelle C.
Bourg J.
Brezinsek S.
Brochard F.
Brun C.
Bruno V.
Bufferand H.
Bureau A.
Burles S.
Camenen Y.
Cantone B.
Caprin E.
Carpentier S.
Caulier G.
Chanet N.
Chellai O.
Chen Y.
Chernyshova M.
Chmielewski P.
Choe W.
Chomiczewska A.
Ciraolo G.
Clairet F.
Coenen J.
Colas L.
Colledani G.
Colnel J.
Coquillat P.
Corbel E.
Corre Y.
Costea S.
Courtois X.
Czarski T.
Daniel R.
Daumas J.
De Combarieu M.
De Temmerman G.
De Vries P.
Dechelle C.
Deguara F.
Dejarnac R.
Delaplanche J.M.
Delmas E.
Delpech L.
Desgranges C.
Devynck P.
Di Genova S.
Diab R.
Diallo A.
Diez M.
Dif-Pradalier G.
Dimitrova M.
Ding B.
Dittmar T.
Doceul L.
Domenes M.
Douai D.
Dougnac H.
Duan X.
Dubus L.
Princeton University
Publisher(s)
IOP Publishing Ltd
Abstract
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.
Volume
62
Issue
4
Language
English
OCDE Knowledge area
Física de plasmas y fluídos Física nuclear
Scopus EID
2-s2.0-85125574424
Source
Nuclear Fusion
ISSN of the container
00295515
Sponsor(s)
This work has been carried out within the framework of the EUROfusion Consortium and the French Research Federation for Fusion Studies and has received funding from the Euratom Research and Training Programme 2014–2018 and 2019–2020 under Grant Agreement No. 633053. The views and opinions expressed herein do not necessarily reflect those of the European Commission.
Sources of information: Directorio de Producción Científica Scopus