Conceptual design of the COMPASS upgrade tokamak.

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F61389021%3A_____%2F17%3A00481637" target="_blank" >RIV/61389021:_____/17:00481637 - isvavai.cz</a>

Nalezeny alternativní kódy

RIV/68407700:21340/17:00319366 RIV/00216208:11320/17:10378070

Výsledek na webu

<a href="http://dx.doi.org/10.1016/j.fusengdes.2017.03.002" target="_blank" >http://dx.doi.org/10.1016/j.fusengdes.2017.03.002</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.fusengdes.2017.03.002" target="_blank" >10.1016/j.fusengdes.2017.03.002</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Conceptual design of the COMPASS upgrade tokamak.

Popis výsledku v původním jazyce

The paper describes the conceptual design of the COMPASS Upgrade (COMPASS-U) tokamak which representsna compact, medium-size, high-magnetic-field and high-density device with a flexible set of poloidal field coils for generation of single, double null and snowflake configurations. In addition, COMPASS-U will be equipped with a closed divertor, which will be operated at high plasma and neutral density and with high optical opacity similar to future reactors. COMPASS-U is capable of addressing some of the key challenges in the field of the plasma exhaust physics, reactor-relevant edge plasma physics, advanced confinement regimes, advanced magnetic configurations and materials for next-step devices. The conceptual design of the individual COMPASS-U systems is presented with emphasis on magnets, support structure and power supply system enhancement.n

Název v anglickém jazyce

Conceptual design of the COMPASS upgrade tokamak.

Popis výsledku anglicky

The paper describes the conceptual design of the COMPASS Upgrade (COMPASS-U) tokamak which representsna compact, medium-size, high-magnetic-field and high-density device with a flexible set of poloidal field coils for generation of single, double null and snowflake configurations. In addition, COMPASS-U will be equipped with a closed divertor, which will be operated at high plasma and neutral density and with high optical opacity similar to future reactors. COMPASS-U is capable of addressing some of the key challenges in the field of the plasma exhaust physics, reactor-relevant edge plasma physics, advanced confinement regimes, advanced magnetic configurations and materials for next-step devices. The conceptual design of the individual COMPASS-U systems is presented with emphasis on magnets, support structure and power supply system enhancement.n

Druh

J_imp - Článek v periodiku v databázi Web of Science

CEP obor

—

OECD FORD obor

20305 - Nuclear related engineering; (nuclear physics to be 1.3);

Projekt

<a href="/cs/project/LM2015045" target="_blank" >LM2015045: COMPASS – Tokamak pro výzkum termonukleární fúze</a><br>

Návaznosti

I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Rok uplatnění

2017

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

—

Svazek periodika

123

Číslo periodika v rámci svazku

October

Stát vydavatele periodika

CH - Švýcarská konfederace

Počet stran výsledku

6

Strana od-do

11-16

Kód UT WoS článku

000418992000003

EID výsledku v databázi Scopus

2-s2.0-85015337483