Speaker
Radomir Panek
Description
See the full Abstract at http://ocs.ciemat.es/EPS2018ABS/pdf/P1.1031.pdf
Conceptual design of the COMPASS-U tokamak
R. Panek, J. Havlicek, M. Hron, R. Dejarnac, M. Komm, J. Urban, V. Weinzettl
and the COMPASS team
Insitute of Plasma Physics of the CAS, Za Slovankou 3, Prague, Czech Republic
The Institute of Plasma Physics of the CAS in Prague has recently started construction of new
COMPASS-U tokamak. It will be a compact, medium-size (R = 0,85 m, a = 0,3 m),
high-magnetic-field (5 T) device. COMPASS-U will be equipped by a flexible set of poloidal
field coils and capable to operate with plasma current up to 2 MA and, therefore, high plasma
density (~ 1020 m-3). The device is designed to generate and test various DEMO relevant
magnetic configurations, such as conventional single null, double null, single and double
snow-flake. The plasma will be heated using 4 MW Neutral Beam Injection (NBI) heating
system with future extension by at least 4 MW Electron Cyclotron Resonant Heating (ECRH|)
system.
The COMPASS-U tokamak will consist of a new vacuum vessel, new toroidal and
poloidal field coils and support structure in a vacuum cryostat. The power supply system will be
upgraded with two new flywheel generators in order to satisfy energy demands of the
high-magnetic field device (approx. 200 MW, 400 MJ). The magnetic coils will be
manufactured of copper and cooled in a cryostat to liquid-nitrogen temperature in order to
decrease their resistivity and lower the ohmic losses associated with the high coil currents (up to
200 kA) at acceptable levels.
COMPASS-U will be equipped with lower and upper closed, high neutral density
divertors. Due to high PB/R ratio COMPASS-U will represent a device which will be able to
perform ITER and DEMO relevant studies in important areas, such as the plasma exhaust or
development of new confinement regimes. The divertors will use conventional materials in the
first stage, however, in the later stage, the liquid metal technology, which represents a
promising solution for the power exhaust in DEMO, will be installed into the lower
COMPASS-U divertor. The metallic first wall will be operated at high temperature (approx.
300 °C) during plasma discharge, which will enable to explore the edge plasma regimes
relevant to ITER and DEMO operation.
The first plasma of the COMPASS-U tokamak is planned for 2022. In this contribution,
we will present the concept of the COMPASS-U tokamak and design of the main tokamak
components.
