Thermal-hydraulic design of water cooled first wall of the fusion reactor under DEMO conditions

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F17%3AN0000010" target="_blank" >RIV/26722445:_____/17:N0000010 - isvavai.cz</a>

Výsledek na webu

<a href="http://dx.doi.org/10.1016/j.fusengdes.2017.03.164" target="_blank" >http://dx.doi.org/10.1016/j.fusengdes.2017.03.164</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.fusengdes.2017.03.164" target="_blank" >10.1016/j.fusengdes.2017.03.164</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Thermal-hydraulic design of water cooled first wall of the fusion reactor under DEMO conditions

Popis výsledku v původním jazyce

The heat loads on the First Wall (FW) of the European DEMO are not yet defined, but when extrapolated from ITER, the loads are expected to exceed the capabilities of current designs. Since DEMO will use Eurofer 97 as the structural material and Pressurized Water Reactor (PWR) conditions at the coolant inlet, the design of the heat sink will be challenging. Indeed, the thermal conductivity of the heat sink material is quite low and the temperature limits are also quite restrictive (between 285 degrees C and 550 degrees C). As in ITER, there are two different kinds of heat sinks that were designed for the FW: the first is the normal heat flux channel and the second is the enhanced heat flux channel. For handling normal heat fluxes (NHF), round tubes with counter-current flow are chosen while for handling enhanced heat fluxes (EHF), the Hypervapotron (HV) channel is chosen. Simulations were carried out to find the limits from the thermal hydraulic point of view using commercial Computational fluid dynamics code STAR-CCM+. For NHF channels after optimization the limit from the thermal hydraulics point of view, was found to be similar to 1.7 MW/m(2), for EHF channels it is similar to 3 MW/m(2).

Název v anglickém jazyce

Thermal-hydraulic design of water cooled first wall of the fusion reactor under DEMO conditions

Popis výsledku anglicky

The heat loads on the First Wall (FW) of the European DEMO are not yet defined, but when extrapolated from ITER, the loads are expected to exceed the capabilities of current designs. Since DEMO will use Eurofer 97 as the structural material and Pressurized Water Reactor (PWR) conditions at the coolant inlet, the design of the heat sink will be challenging. Indeed, the thermal conductivity of the heat sink material is quite low and the temperature limits are also quite restrictive (between 285 degrees C and 550 degrees C). As in ITER, there are two different kinds of heat sinks that were designed for the FW: the first is the normal heat flux channel and the second is the enhanced heat flux channel. For handling normal heat fluxes (NHF), round tubes with counter-current flow are chosen while for handling enhanced heat fluxes (EHF), the Hypervapotron (HV) channel is chosen. Simulations were carried out to find the limits from the thermal hydraulic point of view using commercial Computational fluid dynamics code STAR-CCM+. For NHF channels after optimization the limit from the thermal hydraulics point of view, was found to be similar to 1.7 MW/m(2), for EHF channels it is similar to 3 MW/m(2).

Druh

J_imp - Článek v periodiku v databázi Web of Science

CEP obor

—

OECD FORD obor

20305 - Nuclear related engineering; (nuclear physics to be 1.3);

Projekt

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

Návaznosti

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Rok uplatnění

2017

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

124

Číslo periodika v rámci svazku

November

Stát vydavatele periodika

CH - Švýcarská konfederace

Počet stran výsledku

5

Strana od-do

311-315

Kód UT WoS článku

000419411900066

EID výsledku v databázi Scopus

2-s2.0-85017453435