Reinstalace tokamaku COMPASS-D v ÚFP AV ČR

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F61389021%3A_____%2F06%3A00044741" target="_blank" >RIV/61389021:_____/06:00044741 - isvavai.cz</a>

Výsledek na webu

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DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

Reinstallation of the COMPASS-D tokamak in IPP ASCR

Popis výsledku v původním jazyce

The COMPASS-D tokamak, originally operated by UKAEA at Culham, UK, will be reinstalled at the Institute of Plasma Physics (IPP) AS CR. The COMPASS device was de- signed as a flexible tokamak in the 1980s mainly to explore the MHD physics. Its operation (with D-shaped vessel) began at the Culham Laboratory of the Association EURATOM/UKAEA in 1992. The COMPASS-D tokamak will have the following unique features after putting in operation on IPP Prague. It will be the smallest tokamak with a clear H-mode andITER- relevant geometry. ITER-relevant plasma conditions will be achieved by installation of two neutral beam injection systems (2 x 300 kW), enabling co- and counter- injections. Re- deployment of the existing LH system (400 kW) is also envisaged. A comprehensive set of diagnostics focused mainly on the edge plasma will be installed. The scientific programme proposed for the COMPASS-D tokamak installed in IPP Prague will benefit from these unique features of COMPASS-D.

Název v anglickém jazyce

Reinstallation of the COMPASS-D tokamak in IPP ASCR

Popis výsledku anglicky

The COMPASS-D tokamak, originally operated by UKAEA at Culham, UK, will be reinstalled at the Institute of Plasma Physics (IPP) AS CR. The COMPASS device was de- signed as a flexible tokamak in the 1980s mainly to explore the MHD physics. Its operation (with D-shaped vessel) began at the Culham Laboratory of the Association EURATOM/UKAEA in 1992. The COMPASS-D tokamak will have the following unique features after putting in operation on IPP Prague. It will be the smallest tokamak with a clear H-mode andITER- relevant geometry. ITER-relevant plasma conditions will be achieved by installation of two neutral beam injection systems (2 x 300 kW), enabling co- and counter- injections. Re- deployment of the existing LH system (400 kW) is also envisaged. A comprehensive set of diagnostics focused mainly on the edge plasma will be installed. The scientific programme proposed for the COMPASS-D tokamak installed in IPP Prague will benefit from these unique features of COMPASS-D.

Druh

J_x - Nezařazeno - Článek v odborném periodiku (Jimp, Jsc a Jost)

CEP obor

BL - Fyzika plasmatu a výboje v plynech

OECD FORD obor

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Projekt

<a href="/cs/project/KJB100430602" target="_blank" >KJB100430602: Studium interakce okrajového plazmatu s komponenty první stěny tokamaku.</a><br>

Návaznosti

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)<br>Z - Vyzkumny zamer (s odkazem do CEZ)

Rok uplatnění

2006

Kód důvěrnosti údajů

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Název periodika

Czechoslovak Journal of Physics

ISSN

0011-4626

e-ISSN

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Svazek periodika

56

Číslo periodika v rámci svazku

suppl. B

Stát vydavatele periodika

CZ - Česká republika

Počet stran výsledku

13

Strana od-do

125-137

Kód UT WoS článku

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EID výsledku v databázi Scopus

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