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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

  • 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

    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