DESIGN OF THE COMPASS UPGRADE TOKAMAK

Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F61389021%3A_____%2F17%3A00485300" target="_blank" >RIV/61389021:_____/17:00485300 - isvavai.cz</a>
Result on the web
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DOI - Digital Object Identifier
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Result language
angličtina
Original language name
DESIGN OF THE COMPASS UPGRADE TOKAMAK
Original language description
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.nIn 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.n
Czech name
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Czech description
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Project
<a href="/en/project/8D15001" target="_blank" >8D15001: Project ID 633053 - EUROfusion</a><br>
Continuities
I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Publication year
2017
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

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