COMPASS-U: Tips for cutting-edge nuclear fusion research (Q19954): Difference between revisions
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(Created claim: summary (P836): The main objective of the project is the significant enhancement of the COMPASS Tokamak on a unique device that is currently missing from the European fusion programme (and worldwide). These are flexible tokamak operated in high magnetic field and at high plasma density, capable of addressing many of the recently identified key gaps in the physics of the energy levy in fusion reactors, as well as to explore the innovative geometry of diverter an...) |
(Removed claim: co-financing rate (P837): 71.3499999993463 percent) |
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| Property / co-financing rate: 71.3499999993463 percent / rank | |||||||
Revision as of 15:17, 19 March 2020
Project in Czech Republic financed by DG Regio
| Language | Label | Description | Also known as |
|---|---|---|---|
| English | COMPASS-U: Tips for cutting-edge nuclear fusion research |
Project in Czech Republic financed by DG Regio |
Statements
568,672,658.69 Czech koruna
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797,018,442.46 Czech koruna
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31,880,737.698400002 Euro
0.04 Euro
10 January 2020
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1 December 2017
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31 December 2022
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Ústav fyziky plazmatu AV ČR, v. v. i.
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50°8'4.56"N, 14°28'0.44"E
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18200
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Hlavním cílem projektu je významné vylepšení tokamaku COMPASS na unikátní zařízení, které momentálně chybí v evropském fúzním programu (i celosvětově). Jedná se o flexibilní tokamak provozovaný na vysokém magnetickém poli a při vysoké hustotě plazmatu, schopný řešit mnohé z nedávno identifikovaných klíčových mezer ve fyzice odvodu energie ve fúzních reaktorech, jakožto i zkoumat inovativní geometrie divertoru a pokročilé režimy udržení, klíčové pro tokamaky ITER a DEMO. a. (Czech)
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The main objective of the project is the significant enhancement of the COMPASS Tokamak on a unique device that is currently missing from the European fusion programme (and worldwide). These are flexible tokamak operated in high magnetic field and at high plasma density, capable of addressing many of the recently identified key gaps in the physics of the energy levy in fusion reactors, as well as to explore the innovative geometry of diverter and advanced preservation regimes, key to ITER and DEMO. (English)
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Identifiers
CZ.02.1.01/0.0/0.0/16_019/0000768
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