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The experimental program of Nuclear Research Institute Rez and Institute of Chemical Technology Prague concerning high temperature gas cooled nuclear reactors

The result's identifiers

  • Result code in IS VaVaI

    <a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F60461373%3A22320%2F08%3A00019626" target="_blank" >RIV/60461373:22320/08:00019626 - isvavai.cz</a>

  • Alternative codes found

    RIV/26722445:_____/08:#0000352

  • Result on the web

  • DOI - Digital Object Identifier

Alternative languages

  • Result language

    čeština

  • Original language name

    Experimentální program ÚJV Řež a VŠCHT Praha týkající se vysokoteplotních plynem chlazených jaderných reaktorů

  • Original language description

    This experimental program is connected with new experimental device ? High Temperature Helium Loop (HTHL) which is presently under construction and will simulate the physical and chemical parameters of helium coolant in High Temperature nuclear Reactors(HTR). This device is described in the full text: Pure helium will be used as working medium in he HTHL. Its main physical parameters are the pressure of 7MPa, max. temperature in the test section 1000°C and the flow rate 37,8 kg/h. HTHL will include helium purification system, system of impurities dosage (e.g. CO, CO2, H2, H2O, O2, N2, CH4) and helium sampling. Helium purification experiments and testing of materials under the simulated High Temperature Reactor (HTR) conditions will take place in HTHL.In the future the active channel of the loop will be placed to the experimental nuclear reactor LVR-15, so the experiments could be take place under irradiation. Before performing the experiments in HTHL several problems should be solved

  • Czech name

    Experimentální program ÚJV Řež a VŠCHT Praha týkající se vysokoteplotních plynem chlazených jaderných reaktorů

  • Czech description

    This experimental program is connected with new experimental device ? High Temperature Helium Loop (HTHL) which is presently under construction and will simulate the physical and chemical parameters of helium coolant in High Temperature nuclear Reactors(HTR). This device is described in the full text: Pure helium will be used as working medium in he HTHL. Its main physical parameters are the pressure of 7MPa, max. temperature in the test section 1000°C and the flow rate 37,8 kg/h. HTHL will include helium purification system, system of impurities dosage (e.g. CO, CO2, H2, H2O, O2, N2, CH4) and helium sampling. Helium purification experiments and testing of materials under the simulated High Temperature Reactor (HTR) conditions will take place in HTHL.In the future the active channel of the loop will be placed to the experimental nuclear reactor LVR-15, so the experiments could be take place under irradiation. Before performing the experiments in HTHL several problems should be solved

Classification

  • Type

    D - Article in proceedings

  • CEP classification

    JF - Nuclear energy

  • OECD FORD branch

Result continuities

  • Project

    <a href="/en/project/2A-1TP1%2F100" target="_blank" >2A-1TP1/100: High Temperature Gas Systems.</a><br>

  • Continuities

    Z - Vyzkumny zamer (s odkazem do CEZ)

Others

  • Publication year

    2008

  • Confidentiality

    S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Data specific for result type

  • Article name in the collection

    7th International Power Cycle Chemistry Conference IAPWS

  • ISBN

    978-80-7080-698-2

  • ISSN

  • e-ISSN

  • Number of pages

    16

  • Pages from-to

  • Publisher name

    VŠCHT Praha

  • Place of publication

    Praha

  • Event location

    Praha

  • Event date

    Sep 9, 2008

  • Type of event by nationality

    EUR - Evropská akce

  • UT code for WoS article