Current quench and vessel currents characterisation at the COMPASS tokamak

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F61389021%3A_____%2F22%3A00564322" target="_blank" >RIV/61389021:_____/22:00564322 - isvavai.cz</a>

Nalezeny alternativní kódy

RIV/00216208:11320/22:10456714

Výsledek na webu

<a href="https://iopscience.iop.org/article/10.1088/1361-6587/ac9928" target="_blank" >https://iopscience.iop.org/article/10.1088/1361-6587/ac9928</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1088/1361-6587/ac9928" target="_blank" >10.1088/1361-6587/ac9928</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Current quench and vessel currents characterisation at the COMPASS tokamak

Popis výsledku v původním jazyce

The characterisation of plasma current quench and understanding of its underlying physical processes play a crucial role when designing large fusion devices such as ITER. For the first time, an extensive analysis of the COMPASS tokamak disruption database is presented. A unique set of magnetic diagnostics allows the investigation of local toroidal and poloidal vessel currents, including currents flowing along the open magnetic field lines from the plasma to the vacuum vessel (VV) (i.e., halo currents). Area-normalised current quench times are in agreement with the ITPA 1.67 ms m(-2) lower limit. Extremely fast I-p quench rates of up to 0.6 MA ms(-1) are observed during runaway electron campaigns at COMPASS, which are under the ITPA lower limit. Vertical movement of the plasma column is accelerated by the I-p quench during major disruptions. Toroidal vessel currents of around 2% 4% of the predisruptive plasma current I-disr(p) I-p quench. Net poloidal eddy currents are obtained by Mirnov coils and diamagnetic loop, reaching 3% of I-disr(p) I-p . Geometric features of the VV structure and in-vessel component positions on the poloidal vessel current measurements are discussed.

Název v anglickém jazyce

Current quench and vessel currents characterisation at the COMPASS tokamak

Popis výsledku anglicky

The characterisation of plasma current quench and understanding of its underlying physical processes play a crucial role when designing large fusion devices such as ITER. For the first time, an extensive analysis of the COMPASS tokamak disruption database is presented. A unique set of magnetic diagnostics allows the investigation of local toroidal and poloidal vessel currents, including currents flowing along the open magnetic field lines from the plasma to the vacuum vessel (VV) (i.e., halo currents). Area-normalised current quench times are in agreement with the ITPA 1.67 ms m(-2) lower limit. Extremely fast I-p quench rates of up to 0.6 MA ms(-1) are observed during runaway electron campaigns at COMPASS, which are under the ITPA lower limit. Vertical movement of the plasma column is accelerated by the I-p quench during major disruptions. Toroidal vessel currents of around 2% 4% of the predisruptive plasma current I-disr(p) I-p quench. Net poloidal eddy currents are obtained by Mirnov coils and diamagnetic loop, reaching 3% of I-disr(p) I-p . Geometric features of the VV structure and in-vessel component positions on the poloidal vessel current measurements are discussed.

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

I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Rok uplatnění

2022

Kód důvěrnosti údajů

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

Název periodika

Plasma Physics and Controlled Fusion

ISSN

0741-3335

e-ISSN

1361-6587

Svazek periodika

64

Číslo periodika v rámci svazku

12

Stát vydavatele periodika

GB - Spojené království Velké Británie a Severního Irska

Počet stran výsledku

16

Strana od-do

125010

Kód UT WoS článku

000880428600001

EID výsledku v databázi Scopus

2-s2.0-85142151621