DESIGN OF THE COMPASS UPGRADE TOKAMAK

0485300 - ÚFP 2018 RIV SK eng C - Conference Paper (international conference)
Horáček, Jan - Pánek, Radomír - Havlíček, Josef
DESIGN OF THE COMPASS UPGRADE TOKAMAK.
19th Conference of Czech and Slovak Physicists Proceedings. Košice: Slovak Physical Society, 2017, č. článku OP16. ISBN 978-80-89855-04-9.
[Conference of Czech and Slovak Physicists/19./. Prešov (SK), 04.09.2017-07.09.2017]
R&D Projects: GA MŠMT(CZ) 8D15001
EU Projects: European Commission(XE) 633053 - EUROfusion
Institutional support: RVO:61389021
Keywords : Thermonuclear fusion in the Czech Republic * Tokamak COMPASS Upgrade
OECD category: Fluids and plasma physics (including surface physics)

COMPASS tokamak with ITER-like plasma shape has been put into operation in 2009 in IPP AS CR in Prague. It is equipped by a comprehensive set of diagnostics which enabled to obtain significant results in the field of edge plasma and fusion physics.
In order to enhance the relevance of COMPASS for the future DEMO reactor, an upgrade has been proposed. Using the existing infrastructure the toroidal magnetic field (from 1T upto 5T) and plasma current (from 0.4 upto 2.5MA) will be enhanced by new system of magnetic coils made of copper cooled by Helium vapors (T~70K). The corresponding support structure will have to accommodate extreme electro-magnetic forces acting on the magnetic coils as well as on the new vacuum chamber (R=0.85m, a=0.3m), equipped by two closed divertors (solid tungsten and liquid metal ones). The power supply system will be increased by ~250MJ and 100MW. The additional plasma heating system will consist of Neutral Beam Injectors (4 MW). Such a system will also enable a balanced injection to study the plasma stability at low plasma rotation. We expect divertor plasma power fluxes at the ITER/DEMO level enabling to study relevant power-exhaust physics challenges including the use of liquid metals.

Permanent Link: http://hdl.handle.net/11104/0280386