Impact of a narrow limiter SOL heat flux channel on the ITER first wall panel shaping

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F61389021%3A_____%2F15%3A00443589" target="_blank" >RIV/61389021:_____/15:00443589 - isvavai.cz</a>

Výsledek na webu

<a href="http://dx.doi.org/10.1088/0029-5515/55/3/033019" target="_blank" >http://dx.doi.org/10.1088/0029-5515/55/3/033019</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1088/0029-5515/55/3/033019" target="_blank" >10.1088/0029-5515/55/3/033019</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Impact of a narrow limiter SOL heat flux channel on the ITER first wall panel shaping

Popis výsledku v původním jazyce

The inboard limiters for ITER were initially designed on the assumption that the parallel heat flux density in the scrape-off layer (SOL) could be approximated by a single exponential with decay length ?q. This assumption was found not to be adequate in2012, when infra-red (IR) thermography measurements on the inner column during JET limiter discharges clearly revealed the presence of a narrow heat flux channel adjacent to the last closed flux surface. This near-SOL decay occurs with ?q few mm, much shorter than the main SOL ?q, and can raise the heat flux at the limiter apex a factor up to4 above the value expected from a single, broader exponential. The original logarithmically shaped ITER inner wall first wall panels (FWPs) would be unsuited to handling the power loads produced by such a narrow feature. A multi-machine study involving the C-Mod, COMPASS, DIII-D and TCV tokamaks, employing inner wall IR measurements and/or inner wall reciprocating probes, was initiated

Název v anglickém jazyce

Impact of a narrow limiter SOL heat flux channel on the ITER first wall panel shaping

Popis výsledku anglicky

The inboard limiters for ITER were initially designed on the assumption that the parallel heat flux density in the scrape-off layer (SOL) could be approximated by a single exponential with decay length ?q. This assumption was found not to be adequate in2012, when infra-red (IR) thermography measurements on the inner column during JET limiter discharges clearly revealed the presence of a narrow heat flux channel adjacent to the last closed flux surface. This near-SOL decay occurs with ?q few mm, much shorter than the main SOL ?q, and can raise the heat flux at the limiter apex a factor up to4 above the value expected from a single, broader exponential. The original logarithmically shaped ITER inner wall first wall panels (FWPs) would be unsuited to handling the power loads produced by such a narrow feature. A multi-machine study involving the C-Mod, COMPASS, DIII-D and TCV tokamaks, employing inner wall IR measurements and/or inner wall reciprocating probes, was initiated

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

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

Návaznosti

I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Rok uplatnění

2015

Kód důvěrnosti údajů

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

Název periodika

Nuclear Fusion

ISSN

0029-5515

e-ISSN

—

Svazek periodika

55

Číslo periodika v rámci svazku

3

Stát vydavatele periodika

AT - Rakouská republika

Počet stran výsledku

16

Strana od-do

033019-033019

Kód UT WoS článku

000352020500023

EID výsledku v databázi Scopus

2-s2.0-84924078702