IT’S COMPASS-U: Tokamak for cutting-edge nuclear fusion research (Q19954): Difference between revisions

From EU Knowledge Graph
Jump to navigation Jump to search
(‎Changed label, description and/or aliases in 1 language: remove_english_label)
(‎Changed label, description and/or aliases in 1 language: translated_label)
label / enlabel / en
 
IT’S COMPASS-U: Tokamak for cutting-edge nuclear fusion research

Revision as of 09:17, 22 October 2020

Project in Czech Republic financed by DG Regio
Language Label Description Also known as
English
IT’S COMPASS-U: Tokamak for cutting-edge nuclear fusion research
Project in Czech Republic financed by DG Regio

    Statements

    0 references
    0 references
    568,672,658.69 Czech koruna
    0 references
    22,746,906.35 Euro
    10 January 2020
    0 references
    797,018,442.46 Czech koruna
    0 references
    31,880,737.70 Euro
    10 January 2020
    0 references
    71.35 percent
    0 references
    1 December 2017
    0 references
    31 December 2022
    0 references
    Ústav fyziky plazmatu AV ČR, v. v. i.
    0 references

    50°8'4.56"N, 14°28'0.44"E
    0 references
    18200
    0 references
    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)
    0 references
    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)
    0 references

    Identifiers

    CZ.02.1.01/0.0/0.0/16_019/0000768
    0 references