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Identification
Hosting Legal Entity
Czech Academy of Sciences
Location
Za Slovankou 3, Prague 8 - Libeň, PO: 182 00 (Czech Republic)
Structure
Type Of RI
Single-sited
Coordinating Country
Czech Republic
Status
Status
Current Status:
Operational since 2012
Scientific Description
The COMPASS tokamak is a compact tokamak operated in divertor plasma configuration with ITER-like plasma cross-section shape and at plasma currents up to 0,4 MA. COMPASS is equipped with two NBI injectors enabling either co- or balanced injection and operates in a Type-I ELMy H-mode scenario. A comprehensive set of diagnostic is focused mainly on edge plasma region. The scientific programme is focused on the edge plasma, SOL and divertor physics, namely on pedestal and L-H transition physics, Edge Localized Modes control using magnetic perturbations as well as vertical-kick method, physics of plasma-wall interaction, runaway and disruption physics etc. Due to the ITER plasma shape COMPASS provides data for scalling of these processes towards the ITER tokamak.In addition, COMPASS is extensively used for educational and training activities via organization of international experimental training courses as well involvement in the Fusenet and ERASMUS Mundus Fusion programmes. COMPASS is exploited mainly by the users from the EUROfusion consortium.

RI Keywords
Tokamak, COMPASS, Thermonuclear fusion, Magnetic confinement, Plasma physics
Classifications
RI Category
Nuclear Research Facilities
Scientific Domain
Physics, Astronomy, Astrophysics and Mathematics
ESFRI Domain
Physical Sciences and Engineering
Services
Participation in experimental campaigns of COMPASS

Scientists, in particular from EUROfusion laboratories, but also from international fusion labs are invited to conduct experiments on COMPASS in an Open-access mode based on the selection of the experimental proposal by International Board of Advisors of the COMPASS infrastructure.

Equipment
ELM control systems

Resonant Magnetic Perturbations, Vertical kicks.

COMPASS

Ip =0,4 MA , Bt=2.1T , R=0.56m, a=0.2m, V= 1 m3, pulse duration 1 s; ITER-like coil configuration & shape, X-point plasma, δ= 0 – 0.5, κ =1– 1.8.

Main diagnostics

High resolution edge and core Thomson Scattering systemEdge reflectometry systemTwo reciprocating drivesVIS and IR cameras BeamEmission Spectroscopy on Li beam400 diagnostics magnetic coilsSXR, HXR and bolometrical tomography systemsOther diagnostics systems.

Plasma facing materials

graphite tiles.

Heating system

2 x NBI (2 x 0,4 MW) - co- or balanced injection.

Collaborations
Networks
EURATOM
International Tokamak Physics Activity (ITPA)
Date of last update: 08/06/2017
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