5-9 September 2016
Prague Congress Centre
Europe/Prague timezone

I2.3 Design of the COMPASS Upgrade Tokamak

6 Sep 2016, 09:50
40m
Prague Congress Centre

Prague Congress Centre

5. května 65, Prague, Czech Republic
Board: 3

Speaker

Radomir Panek (Insitute of Plasma Physics CAS)

Description

The COMPASS tokamak with ITER-like plasma shape has been put into operation in 2009 in Institute of Plasma Physics ASCR in Prague. It has been equipped by a comprehensive set of diagnostics for edge and Scrape-Off-Layer (SOL) plasma as well as by a new a system of two Neutral Beam Injectors (NBIs), which enabled to obtain significant results in the field of edge, SOL and divertor physics. In order to enhance the relevance of COMPASS for the future ITER and DEMO relevant studies while benefiting from the knowledge of the team in the field of edge plasma, an upgrade of COMPASS has been proposed. The aim of this upgrade is to use a maximum of the existing infrastructure, while enhancing the parameters of COMPASS mainly in a direction of toroidal magnetic field (up to 5 T) and plasma current (up to 2 MA). To achieve these parameters, new magnetic coils made of copper cooled by nitrogen vapors in order to suppress the Ohmic losses will be used. The corresponding support structure will have to accommodate very high electro-magnetic forces on the magnetic coils as well as on the new vacuum chamber (R = 0.85 m, a = 0.3 m – ITER-like plasma shape). This new vacuum vessel will be equipped by a closed divertor and will enable to generate also the double null magnetic configuration. The power supply system will be modified to provide an energy of approx. 250 MJ and electrical power 100 MW. The plasma will be heated by a flexible heating system, which will consist of five NBIs (4 x 1 MW and 2 x 0.5 MW). Such a system will also enable a balanced injection in order to study the plasma stability at low plasma rotation. Under such conditions, the plasma parameters of COMPASS Upgrade in the plasma edge, SOL and divertor regions will be highly relevant for studies necessary for the future exploitation of ITER as well as the design of DEMO.

Co-authors

Radomir Panek (Insitute of Plasma Physics CAS, Za Slovankou 3, Prague, Czech Republic) the COMPASS team (Insitute of Plasma Physics CAS, Za Slovankou 3, Prague, Czech Republic)

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