IT’S COMPASS-U: Tokamak 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 a significant improvement of COMPASS to a unique device, which is currently missing in the European fusion programme (also globally). It is a flexible tokamak operated on a high magnetic field and high plasma density, capable of addressing many of the recently identified key energy drain gaps in fusion reactors, as well as exploring innovative divertor geometry and advanced maintenance modes, key for ITER and...) |
(Changed label, description and/or aliases in 2 languages: Changing unique label-description pair) |
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description / en | description / en | ||
Project in Czech Republic | Project Q19954 in Czech Republic | ||
description / cs | description / cs | ||
Projekt v | Projekt Q19954 v Czechia |
Revision as of 18:06, 28 October 2020
Project Q19954 in Czech Republic
Language | Label | Description | Also known as |
---|---|---|---|
English | IT’S COMPASS-U: Tokamak for cutting-edge nuclear fusion research |
Project Q19954 in Czech Republic |
Statements
568,672,658.69 Czech koruna
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797,018,442.46 Czech koruna
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71.35 percent
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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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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 a significant improvement of COMPASS to a unique device, which is currently missing in the European fusion programme (also globally). It is a flexible tokamak operated on a high magnetic field and high plasma density, capable of addressing many of the recently identified key energy drain gaps in fusion reactors, as well as exploring innovative divertor geometry and advanced maintenance modes, key for ITER and DEMO. a. (English)
22 October 2020
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Identifiers
CZ.02.1.01/0.0/0.0/16_019/0000768
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