Estimation of the contribution of gaps to tritium retention in the divertor of ITER

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F61389021%3A_____%2F14%3A00427967" target="_blank" >RIV/61389021:_____/14:00427967 - isvavai.cz</a>

Výsledek na webu

<a href="http://dx.doi.org/10.1088/0031-8949/2014/T159/014063" target="_blank" >http://dx.doi.org/10.1088/0031-8949/2014/T159/014063</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1088/0031-8949/2014/T159/014063" target="_blank" >10.1088/0031-8949/2014/T159/014063</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Estimation of the contribution of gaps to tritium retention in the divertor of ITER

Popis výsledku v původním jazyce

An estimation of the contribution of gaps to beryllium deposition and resulting tritium retention in the divertor of ITER is presented. Deposition of beryllium layers in gaps of the full tungsten divertor is simulated with the 3D-GAPS code. For gaps aligned along the poloidal direction, non-shaped and shaped solutions are compared. Plasma and impurity ion fluxes from Schmid (2008 Nucl. Fusion 48 105004) are used as input. Ion penetration into gaps is considered to be geometrical along magnetic field lines. The effect of realistic ion penetration into gaps is discussed. In total, gaps in the divertor are estimated to contribute about 0.3 mgT s1 to the overall tritium retention dominated by toroidal gaps, which are not shaped. This amount corresponds toabout 7800 ITER discharges up to the safety limit of 1 kg in-vessel tritium; excluding, however, tritium release during wall baking and retention at plasma-wetted and remote areas.

Název v anglickém jazyce

Estimation of the contribution of gaps to tritium retention in the divertor of ITER

Popis výsledku anglicky

An estimation of the contribution of gaps to beryllium deposition and resulting tritium retention in the divertor of ITER is presented. Deposition of beryllium layers in gaps of the full tungsten divertor is simulated with the 3D-GAPS code. For gaps aligned along the poloidal direction, non-shaped and shaped solutions are compared. Plasma and impurity ion fluxes from Schmid (2008 Nucl. Fusion 48 105004) are used as input. Ion penetration into gaps is considered to be geometrical along magnetic field lines. The effect of realistic ion penetration into gaps is discussed. In total, gaps in the divertor are estimated to contribute about 0.3 mgT s1 to the overall tritium retention dominated by toroidal gaps, which are not shaped. This amount corresponds toabout 7800 ITER discharges up to the safety limit of 1 kg in-vessel tritium; excluding, however, tritium release during wall baking and retention at plasma-wetted and remote areas.

Druh

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

CEP obor

BL - Fyzika plasmatu a výboje v plynech

OECD FORD obor

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Projekt

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Návaznosti

I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Rok uplatnění

2014

Kód důvěrnosti údajů

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

Název periodika

Physica Scripta

ISSN

0031-8949

e-ISSN

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Svazek periodika

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Číslo periodika v rámci svazku

T159

Stát vydavatele periodika

GB - Spojené království Velké Británie a Severního Irska

Počet stran výsledku

4

Strana od-do

014063-014063

Kód UT WoS článku

000334847800064

EID výsledku v databázi Scopus

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