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HELCZA - High heat flux test facility for testing ITER EU first wall components

The result's identifiers

  • Result code in IS VaVaI

    <a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F17%3AN0000011" target="_blank" >RIV/26722445:_____/17:N0000011 - isvavai.cz</a>

  • Alternative codes found

    RIV/61389021:_____/17:00480958

  • Result on the web

    <a href="http://dx.doi.org/10.1016/j.fusengdes.2017.03.059" target="_blank" >http://dx.doi.org/10.1016/j.fusengdes.2017.03.059</a>

  • DOI - Digital Object Identifier

    <a href="http://dx.doi.org/10.1016/j.fusengdes.2017.03.059" target="_blank" >10.1016/j.fusengdes.2017.03.059</a>

Alternative languages

  • Result language

    angličtina

  • Original language name

    HELCZA - High heat flux test facility for testing ITER EU first wall components

  • Original language description

    The ITER first wall panels are exposed directly to thermonuclear plasma and must extract heat loads of approximately 2 MW/m2 (normal heat flux) to 4.7 MW/m2 (enhanced heat flux). The panels are qualified through high heat flux cyclic testing before installation in ITER. Initially, the first wall panel prototypes will undergo full-power tests, they will be followed by the pre-series panels and finally the series ones. The experimental complex HELCZA (High Energy Load CZech Assembly) has been completed and is currently in the commissioning phase. HELCZA shall be optimised to provide a cyclic heating of the ITER EU first wall panels with a heat flux in the multi-MW/m2 range using an 800 kW electron beam. On a reduced area it is possible to reach GW/m2 scale. Total available test area in HELCZA is 4 m2 depending on the experimental setup. Operational conditions of the HELCZA facility enable the temperature of the cooling water to be set between 25 °C and 320 °C, within a pressure range up to 15 MPa. The cooling system provides an optimal flow rate up to 40 m3/h independent of the pressure.

  • 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

    4

  • Pages from-to

    187-190

  • UT code for WoS article

    000419411900040

  • EID of the result in the Scopus database

    2-s2.0-85015782575