Predictive and interpretative modelling of ASDEX-upgrade liquid metal divertor experiment

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F61389021%3A_____%2F23%3A00583457" target="_blank" >RIV/61389021:_____/23:00583457 - isvavai.cz</a>

Nalezeny alternativní kódy

RIV/68407700:21340/23:00373520

Výsledek na webu

<a href="https://www.sciencedirect.com/science/article/pii/S0920379623004684?via%3Dihub" target="_blank" >https://www.sciencedirect.com/science/article/pii/S0920379623004684?via%3Dihub</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.fusengdes.2023.113886" target="_blank" >10.1016/j.fusengdes.2023.113886</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Predictive and interpretative modelling of ASDEX-upgrade liquid metal divertor experiment

Popis výsledku v původním jazyce

A liquid metal Capillary Porous System (CPS) test module filled with tin was studied in the ASDEX Upgrade (AUG) outer divertor. The CPS module was flush mounted as part of a target tile and exposed using the AUG divertor manipulator. In order to predict tin erosion from the designed module under typical AUG divertor loading conditions, the experiment was interpreted using the HeatLMD code. Preceding test exposures of the CPS in the high heat flux facility GLADIS were performed and interpreted by modelling to quantify the thermo-mechanical properties of the module. The results for the reference AUG discharge indicated a total of 2.6 × 1017 tin atoms (51 μg) would be eroded during the exposure, predominantly through temperature enhanced sputtering. The vapour cooling power was predicted to be negligible (5 kW/m2at the end of a 5 s exposure with heat flux from the plasma of 2 MW/m2). The module was expected to be compatible with plasma operation, with tin erosion too low for any significant effect on the plasma performance. However, interpretative modelling of the experimental discharge with the highest exposure time yielded significantly lower tin erosion than observed. To be attributed to tin radiation the experimentally observed increase in total radiative power (1.5 MW) would require 2 × 1018 tin atoms (peak calculated erosion rate) radiating in the core plasma. This would require every tin atom eroded, to reach the core, which is unlikely.

Název v anglickém jazyce

Predictive and interpretative modelling of ASDEX-upgrade liquid metal divertor experiment

Popis výsledku anglicky

A liquid metal Capillary Porous System (CPS) test module filled with tin was studied in the ASDEX Upgrade (AUG) outer divertor. The CPS module was flush mounted as part of a target tile and exposed using the AUG divertor manipulator. In order to predict tin erosion from the designed module under typical AUG divertor loading conditions, the experiment was interpreted using the HeatLMD code. Preceding test exposures of the CPS in the high heat flux facility GLADIS were performed and interpreted by modelling to quantify the thermo-mechanical properties of the module. The results for the reference AUG discharge indicated a total of 2.6 × 1017 tin atoms (51 μg) would be eroded during the exposure, predominantly through temperature enhanced sputtering. The vapour cooling power was predicted to be negligible (5 kW/m2at the end of a 5 s exposure with heat flux from the plasma of 2 MW/m2). The module was expected to be compatible with plasma operation, with tin erosion too low for any significant effect on the plasma performance. However, interpretative modelling of the experimental discharge with the highest exposure time yielded significantly lower tin erosion than observed. To be attributed to tin radiation the experimentally observed increase in total radiative power (1.5 MW) would require 2 × 1018 tin atoms (peak calculated erosion rate) radiating in the core plasma. This would require every tin atom eroded, to reach the core, which is unlikely.

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

<a href="/cs/project/GA22-03950S" target="_blank" >GA22-03950S: Interakce plazmatu s tepelným štítem fúzních reaktorů</a><br>

Návaznosti

I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Rok uplatnění

2023

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

1873-7196

Svazek periodika

194

Číslo periodika v rámci svazku

June

Stát vydavatele periodika

NL - Nizozemsko

Počet stran výsledku

7

Strana od-do

113886

Kód UT WoS článku

001027611100001

EID výsledku v databázi Scopus

2-s2.0-85162985263