Evaluation of first wall heat fluxes due to magnetic perturbations for a range of ITER scenarios

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F00216208%3A11320%2F15%3A10319572" target="_blank" >RIV/00216208:11320/15:10319572 - isvavai.cz</a>

Nalezeny alternativní kódy

RIV/61389021:_____/15:00445031

Výsledek na webu

<a href="http://dx.doi.org/10.1016/j.jnucmat.2014.11.121" target="_blank" >http://dx.doi.org/10.1016/j.jnucmat.2014.11.121</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.jnucmat.2014.11.121" target="_blank" >10.1016/j.jnucmat.2014.11.121</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Evaluation of first wall heat fluxes due to magnetic perturbations for a range of ITER scenarios

Popis výsledku v původním jazyce

The proposed use of magnetic perturbations for edge-localized mode (ELM) control in ITER poses a number of integration issues, among them the localized heat fluxes (footprints) on the plasma-facing components (PFCs). They may provide the benefit of spreading the heat flux, thus reducing its peak value, but they may cause a localized erosion of the PFCs. We present calculations of heat fluxes for a range of ITER plasma parameters. The efficiency of our method enables us to perform calculations for a range of assumptions on the SOL width and to optimize the coil configuration to yield the largest power flux spreading. The optimal coil configuration is not sensitive on SOL parameters and is also close to the one which is considered optimal for ELM control. The proximity of footprints may cause significant power loads on the upper wall. (C) 2014 The Authors. Published by Elsevier B.V. This is an open access article under the CC BY-NC-ND license.

Název v anglickém jazyce

Evaluation of first wall heat fluxes due to magnetic perturbations for a range of ITER scenarios

Popis výsledku anglicky

The proposed use of magnetic perturbations for edge-localized mode (ELM) control in ITER poses a number of integration issues, among them the localized heat fluxes (footprints) on the plasma-facing components (PFCs). They may provide the benefit of spreading the heat flux, thus reducing its peak value, but they may cause a localized erosion of the PFCs. We present calculations of heat fluxes for a range of ITER plasma parameters. The efficiency of our method enables us to perform calculations for a range of assumptions on the SOL width and to optimize the coil configuration to yield the largest power flux spreading. The optimal coil configuration is not sensitive on SOL parameters and is also close to the one which is considered optimal for ELM control. The proximity of footprints may cause significant power loads on the upper wall. (C) 2014 The Authors. Published by Elsevier B.V. This is an open access article under the CC BY-NC-ND license.

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

<a href="/cs/project/GAP205%2F11%2F2341" target="_blank" >GAP205/11/2341: Kontrola okrajových nestabilit plazmatu v tokamacích pomocí vnějších magnetických poruch</a><br>

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

Journal of Nuclear Materials

ISSN

0022-3115

e-ISSN

—

Svazek periodika

463

Číslo periodika v rámci svazku

Aug

Stát vydavatele periodika

NL - Nizozemsko

Počet stran výsledku

5

Strana od-do

406-410

Kód UT WoS článku

000358467200081

EID výsledku v databázi Scopus

2-s2.0-84937729559