High heat flux limits of the fusion reactor water-cooled first wall

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F61389021%3A_____%2F19%3A00519145" target="_blank" >RIV/61389021:_____/19:00519145 - isvavai.cz</a>

Nalezeny alternativní kódy

RIV/68407700:21220/19:00332496

Výsledek na webu

<a href="https://www.sciencedirect.com/science/article/pii/S1738573318304182?via%3Dihub" target="_blank" >https://www.sciencedirect.com/science/article/pii/S1738573318304182?via%3Dihub</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.net.2019.03.013" target="_blank" >10.1016/j.net.2019.03.013</a>

Jazyk výsledku

angličtina

Název v původním jazyce

High heat flux limits of the fusion reactor water-cooled first wall

Popis výsledku v původním jazyce

The water-cooled WCLL blanket is one of the possible candidates for the blanket of the fusion power reactors. The plasma-facing first wall manufactured from the reduced-activation ferritic-martensitic steel Eurofer97 will be cooled with water at a typical pressurized water reactor (PWR) conditions. According to new estimates, the first wall will be exposed to peak heat fluxes up to 7 MW/m(2) while the maximum operated temperature of Eurofer97 is set to 550 degrees C. The performed analysis shows the capability of the designed flat first wall concept to remove heat flux without exceeding the maximum Eurofer97 operating temperature only up to 0.75 MW/m(2). Several heat transfer enhancement methods (turbulator promoters), structural modifications, and variations of parameters were analysed. The effects of particular modifications on the wall temperature were evaluated using thermo-hydraulic three-dimensional numerical simulation. The analysis shows the negligible effect of the turbulators. By the combination of the proposed modifications, the permitted heat flux was increased up to 1.69 MW/m(2) only. The results indicate the necessity of the re-evaluation of the existing first wall concepts.

Název v anglickém jazyce

High heat flux limits of the fusion reactor water-cooled first wall

Popis výsledku anglicky

The water-cooled WCLL blanket is one of the possible candidates for the blanket of the fusion power reactors. The plasma-facing first wall manufactured from the reduced-activation ferritic-martensitic steel Eurofer97 will be cooled with water at a typical pressurized water reactor (PWR) conditions. According to new estimates, the first wall will be exposed to peak heat fluxes up to 7 MW/m(2) while the maximum operated temperature of Eurofer97 is set to 550 degrees C. The performed analysis shows the capability of the designed flat first wall concept to remove heat flux without exceeding the maximum Eurofer97 operating temperature only up to 0.75 MW/m(2). Several heat transfer enhancement methods (turbulator promoters), structural modifications, and variations of parameters were analysed. The effects of particular modifications on the wall temperature were evaluated using thermo-hydraulic three-dimensional numerical simulation. The analysis shows the negligible effect of the turbulators. By the combination of the proposed modifications, the permitted heat flux was increased up to 1.69 MW/m(2) only. The results indicate the necessity of the re-evaluation of the existing first wall concepts.

Druh

J_imp - Článek v periodiku v databázi Web of Science

CEP obor

—

OECD FORD obor

10304 - Nuclear physics

Projekt

<a href="/cs/project/EF16_019%2F0000778" target="_blank" >EF16_019/0000778: Centrum pokročilých aplikovaných přírodních věd</a><br>

Návaznosti

I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Rok uplatnění

2019

Kód důvěrnosti údajů

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

Název periodika

Nuclear Engineering and Technology

ISSN

1738-5733

e-ISSN

—

Svazek periodika

51

Číslo periodika v rámci svazku

5

Stát vydavatele periodika

KR - Korejská republika

Počet stran výsledku

10

Strana od-do

1251-1260

Kód UT WoS článku

000473127300007

EID výsledku v databázi Scopus

2-s2.0-85068056476