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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

  • Czech description

Classification

  • Type

    J<sub>imp</sub> - Article in a specialist periodical, which is included in the Web of Science database

  • CEP classification

  • 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

  • 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