Remote operation of the vertical plasma stabilization @ the GOLEM tokamak for the plasma physics education

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21340%2F15%3A00235955" target="_blank" >RIV/68407700:21340/15:00235955 - isvavai.cz</a>

Nalezeny alternativní kódy

RIV/61389021:_____/15:00454864

Výsledek na webu

<a href="http://www.sciencedirect.com/science/article/pii/S0920379615300740" target="_blank" >http://www.sciencedirect.com/science/article/pii/S0920379615300740</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.fusengdes.2015.06.044" target="_blank" >10.1016/j.fusengdes.2015.06.044</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Remote operation of the vertical plasma stabilization @ the GOLEM tokamak for the plasma physics education

Popis výsledku v původním jazyce

The GOLEM tokamak at the Czech Technical University has been established as an educational tokamak device for domestic and foreign students. Remote participation in the scope of several laboratory practices, plasma physics schools and workshops has beensuccessfully performed from abroad. A new enhancement allowing understandable remote control of vertical plasma position in two modes i) predefined and ii) feedback control is presented. It allows to drive the current in the stabilization coils in any time-dependent scenario, which can include as a parameter the actual plasma position measured by magnetic diagnostics. Arbitrary movement of the plasma column in a vertical direction, stabilization of the plasma column in the center of the tokamak vessel as well as prolongation/shortening of plasma life according to the remotely defined request are demonstrated.

Název v anglickém jazyce

Remote operation of the vertical plasma stabilization @ the GOLEM tokamak for the plasma physics education

Popis výsledku anglicky

The GOLEM tokamak at the Czech Technical University has been established as an educational tokamak device for domestic and foreign students. Remote participation in the scope of several laboratory practices, plasma physics schools and workshops has beensuccessfully performed from abroad. A new enhancement allowing understandable remote control of vertical plasma position in two modes i) predefined and ii) feedback control is presented. It allows to drive the current in the stabilization coils in any time-dependent scenario, which can include as a parameter the actual plasma position measured by magnetic diagnostics. Arbitrary movement of the plasma column in a vertical direction, stabilization of the plasma column in the center of the tokamak vessel as well as prolongation/shortening of plasma life according to the remotely defined request are demonstrated.

Druh

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

CEP obor

BL - Fyzika plasmatu a výboje v plynech

OECD FORD obor

—

Projekt

—

Návaznosti

S - Specificky vyzkum na vysokych skolach

Rok uplatnění

2015

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

96-97

Číslo periodika v rámci svazku

10

Stát vydavatele periodika

CH - Švýcarská konfederace

Počet stran výsledku

6

Strana od-do

974-979

Kód UT WoS článku

000364255900202

EID výsledku v databázi Scopus

2-s2.0-84942827535