High heat flux limits of the fusion reactor water-cooled first wall
The result's identifiers
Result code in 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>
Alternative codes found
RIV/68407700:21220/19:00332496
Result on the web
<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>
Alternative languages
Result language
angličtina
Original language name
High heat flux limits of the fusion reactor water-cooled first wall
Original language description
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.
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
10304 - Nuclear physics
Result continuities
Project
<a href="/en/project/EF16_019%2F0000778" target="_blank" >EF16_019/0000778: Center for advanced applied science</a><br>
Continuities
I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace
Others
Publication year
2019
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Data specific for result type
Name of the periodical
Nuclear Engineering and Technology
ISSN
1738-5733
e-ISSN
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Volume of the periodical
51
Issue of the periodical within the volume
5
Country of publishing house
KR - KOREA, REPUBLIC OF
Number of pages
10
Pages from-to
1251-1260
UT code for WoS article
000473127300007
EID of the result in the Scopus database
2-s2.0-85068056476