Preliminary design of the COMPASS upgrade tokamak

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F61389021%3A_____%2F21%3A00543244" target="_blank" >RIV/61389021:_____/21:00543244 - isvavai.cz</a>

Nalezeny alternativní kódy

RIV/00216208:11320/21:10432145 RIV/49777513:23220/21:43961914 RIV/68407700:21340/21:00350622

Výsledek na webu

<a href="https://www.sciencedirect.com/science/article/pii/S0920379621002660?via%3Dihub" target="_blank" >https://www.sciencedirect.com/science/article/pii/S0920379621002660?via%3Dihub</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.fusengdes.2021.112490" target="_blank" >10.1016/j.fusengdes.2021.112490</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Preliminary design of the COMPASS upgrade tokamak

Popis výsledku v původním jazyce

COMPASS Upgrade is a new medium size, high magnetic field tokamak (R = 0.9 m, Bt = 5 T, Ip = 2 MA) currently under design in the Czech Republic. It will provide unique capabilities for addressing some of the key challenges in plasma exhaust physics, advanced confinement modes and advanced plasma configurations as well as testing new plasma facing materials and liquid metal divertor concepts. This paper contains an overview of the preliminary engineering design of the main systems of the COMPASS Upgrade tokamak (vacuum vessel, central solenoid and poloidal field coils, toroidal field coils, support structure, cryostat, cryogenic system, power supply system and machine monitoring and protection system). The description of foreseen auxiliary plasma heating systems and plasma diagnostics is also provided as well as a summary of expected plasma performance and available plasma configurations.

Název v anglickém jazyce

Preliminary design of the COMPASS upgrade tokamak

Popis výsledku anglicky

COMPASS Upgrade is a new medium size, high magnetic field tokamak (R = 0.9 m, Bt = 5 T, Ip = 2 MA) currently under design in the Czech Republic. It will provide unique capabilities for addressing some of the key challenges in plasma exhaust physics, advanced confinement modes and advanced plasma configurations as well as testing new plasma facing materials and liquid metal divertor concepts. This paper contains an overview of the preliminary engineering design of the main systems of the COMPASS Upgrade tokamak (vacuum vessel, central solenoid and poloidal field coils, toroidal field coils, support structure, cryostat, cryogenic system, power supply system and machine monitoring and protection system). The description of foreseen auxiliary plasma heating systems and plasma diagnostics is also provided as well as a summary of expected plasma performance and available plasma configurations.

Druh

J_imp - Článek v periodiku v databázi Web of Science

CEP obor

—

OECD FORD obor

10305 - Fluids and plasma physics (including surface physics)

Projekt

Výsledek vznikl pri realizaci vícero projektů. Více informací v záložce Projekty.

Návaznosti

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Rok uplatnění

2021

Kód důvěrnosti údajů

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

Název periodika

Fusion Engineering and Design

ISSN

0920-3796

e-ISSN

1873-7196

Svazek periodika

169

Číslo periodika v rámci svazku

August

Stát vydavatele periodika

CH - Švýcarská konfederace

Počet stran výsledku

13

Strana od-do

112490

Kód UT WoS článku

000669445900002

EID výsledku v databázi Scopus

2-s2.0-85102967377