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The COMPASS tokamak (derived from COMPact ASSembly) in Prague[1][2][3] is the main experimental facility of Tokamak department of Institute of Plasma Physics of the Czech Academy of Sciences since 2006.[4] It was designed in the 1980s in the British Culham Science Centre as a flexible research facility dedicated mostly to plasma physics studies in circular and D-shaped plasmas.

History

The first plasma in COMPASS "broke down" in 1989 in a C-shaped vacuum vessel, i.e., in a simpler vessel with a circular cross-section. Pioneering experiments followed, including for example the ITER-relevant tests of magnetic field correction with saddle coils for Resonant magnetic perturbations (RMP) experiments or experiments with non-inductive current drive in plasma.

The operation of tokamak restarted with a D-shaped vacuum vessel in 1992. The operation mode with high plasma confinement (H-mode) was achieved, which represents a reference operation ("standard scenario") for the ITER tokamak. The COMPASS tokamak with its size (major radius 0.6 m and height of the vessel approx. 0.7 m) ranks to smaller tokamaks capable of the H-mode operation. Importantly, due to its size and shape the COMPASS plasmas correspond to one tenth (in the linear scale) of the ITER plasmas. At present, besides COMPASS there are only two operational tokamaks in Europe with ITER-like configuration capable of regime with the high plasma confinement. It is the Joint European Torus (JET) and the German tokamak ASDEX Upgrade (Institut für Plasmaphysik, Garching, Germany). JET is the biggest experimental device of this type in the world.

In 2002, British scientists started alternative research on larger, spherical tokamak MAST. Operation of COMPASS was discontinued due to insufficient resources for operation of both tokamaks, however, the research program foreseen for the latter tokamak was not concluded. Due to its important and not completely realised opportunities - and, in particular, due to its direct relevance to the ITER project - the facility was offered for free by the European Commission and UKAEA to the Institute of Plasma Physics AS CR in Prague in autumn 2004. The Prague institute has been coordinating research in thermonuclear fusion in the Czech Republic in the framework of EURATOM since 1999. Team of physicists from the institute has a long-time experience in this field of research including operation of a small tokamak CASTOR. The European Commission has declared that the institute is fully competent to operate the tokamak COMPASS.
Parameters of the tokamak COMPASS
Parameters Values[5] Values after planned upgrade in 2021[6]
Major radius R 0.56 m 0.84 m
Minor radius a 0.23 m 0.28 m
Plasma current Ip (max) 360 kA 2 MA
Magnetic field BT 0.9 T - 2.1 T 5 T
Vacuum pressure 1×10−6 Pa
Elongation 1.8
Plasma shape D, SND, elliptical, circular
Pulse length(max) ~ 0.5 s 5 s
Beam heating PNBI 40 keV 2 × 0.3 MW 4-5 MW
See also

List of fusion experiments
ELM (Edge Localized Mode)
Ball-pen probe
Langmuir probe
Thomson scattering
Resonant magnetic perturbations

References

Pánek, R.; O. Bilyková; V. Fuchs; M. Hron; P. Chráska; P. Pavlo; J. Stöckel; J. Urban; V. Weinzettl; J. Zajac; F. Žáček (2006). "Reinstallation of the COMPASS-D tokamak in IPP ASCR". Czechoslovak Journal of Physics. 56 (2): 125–137. Bibcode:2006CzJPh..56B.125P. doi:10.1007/s10582-006-0188-1. ISSN 1572-9486. S2CID 53056977.
Weinzettl, V.; R. Panek; M. Hron; J. Stockel; F. Zacek; J.Havlicek; P.Bilkova; D.I.Naydenkova; P.Hacek; J.Zajac; R.Dejarnac; J.Horacek; J. Adamek; J. Mlynar; F. Janky; M. Aftanas; P. Bohm; J. Brotankova; D. Sestak; I. Duran; R. Melich; D. Jares; J. Ghosh; G. Anda; G. Veres; A. Szappanos; S. Zoletnik; M. Berta; V.F. Shevchenko; R. Scannell; M. Walsh; H.W. Müller; V. Igochine; A. Silva; M. Manso; R. Gomes; Tsv. Popov; D. Sarychev; V.K. Kiselov; S. Nanobashvili (2011). "Overview of the COMPASS diagnostics". Fusion Engineering and Design. 86 (6–8): 1224–1231. doi:10.1016/j.fusengdes.2010.12.024.
Panek, R.; J. Adamek; M. Aftanas; P. Bilkova; P. Böhm; F. Brochard; P. Cahyna; J. Cavalier; R.Dejarnac; M. Dimitrova; O. Grover; J. Harrison; P. Hacek; J. Havlicek; A. Havranek; J. Horacek; M. Hron; M. Imrisek; F. Janky; A. Kirk; M. Komm; K. Kovarik; J. Krbec; L. Kripner; T. Markovic; K. Mitosinkova; J. Mlynar; D. Naydenkova; M. Peterka; J. Seidl; J. Stöckel; E. Stefanikova; M. Tomes; J. Urban; P. Vondracek; M. Varavin; J. Varju; V. Weinzettl; J. Zajac (2015). "Status of the COMPASS tokamak and characterization of the first H-mode". Plasma Phys. Control. Fusion. 58 (1): 014015. Bibcode:2016PPCF...58a4015P. doi:10.1088/0741-3335/58/1/014015.
"Tokamak". www.ipp.cas.cz. Retrieved 2020-06-25.
COMPASS on the Institute of Plasma Physics of CAS

"COMPASS Upgrade on the Institute of Plasma Physics of CAS".

External links

Magnetic fusion in the Czech Republic
Diagnostic system on COMPASS

https://iopscience.iop.org/article/10.1088/0741-3335/58/1/014015

vte

Fusion power, processes and devices
Core topics

Nuclear fusion
Timeline List of experiments Nuclear power Nuclear reactor Atomic nucleus Fusion energy gain factor Lawson criterion Magnetohydrodynamics Neutron Plasma

Processes,
methods
Confinement
type
Gravitational

Alpha process Triple-alpha process CNO cycle Fusor Helium flash Nova
remnants Proton-proton chain Carbon-burning Lithium burning Neon-burning Oxygen-burning Silicon-burning R-process S-process

Magnetic

Dense plasma focus Field-reversed configuration Levitated dipole Magnetic mirror
Bumpy torus Reversed field pinch Spheromak Stellarator Tokamak
Spherical Z-pinch

Inertial

Bubble (acoustic) Laser-driven Magnetized Liner Inertial Fusion

Electrostatic

Fusor Polywell

Other forms

Colliding beam Magnetized target Migma Muon-catalyzed Pyroelectric

Devices, experiments
Magnetic confinement
Tokamak

International

ITER DEMO PROTO

Americas

Canada STOR-M United States Alcator C-Mod ARC
SPARC DIII-D Electric Tokamak LTX NSTX
PLT TFTR Pegasus Brazil ETE Mexico Novillo [es]

Asia,
Oceania

China CFETR EAST
HT-7 SUNIST India ADITYA SST-1 Japan JT-60 QUEST [ja] Pakistan GLAST South Korea KSTAR

Europe

European Union JET Czech Republic COMPASS GOLEM [cs] France TFR WEST Germany ASDEX Upgrade TEXTOR Italy FTU IGNITOR Portugal ISTTOK Russia T-15 Switzerland TCV United Kingdom MAST-U START STEP

Stellarator
Americas

United States CNT CTH HIDRA HSX Model C NCSX Costa Rica SCR-1

Asia,
Oceania

Australia H-1NF Japan Heliotron J LHD

Europe

Germany WEGA Wendelstein 7-AS Wendelstein 7-X Spain TJ-II Ukraine Uragan-2M
Uragan-3M [uk]

RFP

Italy RFX United States MST

Magnetized target

Canada SPECTOR United States LINUS FRX-L – FRCHX Fusion Engine

Other

Russia GDT United States Astron LDX Lockheed Martin CFR MFTF
TMX Perhapsatron PFRC Riggatron SSPX United Kingdom Sceptre Trisops ZETA

Inertial confinement
Laser
Americas

United States Argus Cyclops Janus LIFE Long path NIF Nike Nova OMEGA Shiva

Asia

Japan GEKKO XII

Europe

European Union HiPER Czech Republic Asterix IV (PALS) France LMJ LULI2000 Russia ISKRA United Kingdom Vulcan

Non-laser

United States PACER Z machine

Applications

Thermonuclear weapon
Pure fusion weapon

International Fusion Materials Irradiation Facility ITER Neutral Beam Test Facility

Physics Encyclopedia

World

Index

Hellenica World - Scientific Library

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