Thermal-hydraulic design of water cooled first wall of the fusion reactor under DEMO conditions
The result's identifiers
Result code in 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>
Result on the web
<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>
Alternative languages
Result language
angličtina
Original language name
Thermal-hydraulic design of water cooled first wall of the fusion reactor under DEMO conditions
Original language description
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).
Czech name
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Czech description
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Classification
Type
J<sub>imp</sub> - Article in a specialist periodical, which is included in the Web of Science database
CEP classification
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OECD FORD branch
20305 - Nuclear related engineering; (nuclear physics to be 1.3);
Result continuities
Project
Result was created during the realization of more than one project. More information in the Projects tab.
Continuities
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)
Others
Publication year
2017
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Data specific for result type
Name of the periodical
Fusion Engineering and Design
ISSN
0920-3796
e-ISSN
1873-7196
Volume of the periodical
124
Issue of the periodical within the volume
November
Country of publishing house
CH - SWITZERLAND
Number of pages
5
Pages from-to
311-315
UT code for WoS article
000419411900066
EID of the result in the Scopus database
2-s2.0-85017453435