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    Wyświetlanie 1-3 z 3
    Tytuł:
    Minor actinides impact on basic safety parameters of medium-sized sodium-cooled fast reactor
    Autorzy:
    Darnowski, P.
    Uzunow, N.
    Powiązania:
    https://bibliotekanauki.pl/articles/147617.pdf
    Data publikacji:
    2015
    Wydawca:
    Instytut Chemii i Techniki Jądrowej
    Tematy:
    fast reactor safety
    MCNP5
    sodium-cooled fast reactor
    nuclear waste transmutation
    Opis:
    An analysis of the infl uence of addition of minor actinides (MA) to the fast reactor fuel on the most important safety characteristics was performed. A special emphasis was given to the total control rods worth in order to describe qualitatively and quantitatively its change with MA content. All computations were performed with a homogeneous assembly model of modifi ed BN-600 sodium-cooled fast reactor core with 0, 3 and 6% of MA. A model was prepared for the Monte Carlo neutron transport code MCNP5 for fresh fuel in the beginning-oflife (BOL) state. Additionally, some other parameters, such as Doppler constant, sodium void reactivity, delayed neutron fraction, neutron fl uxes and neutron spectra distribution, were computed and their change with MA content was investigated. Study indicates that the total control rods worth (CRW) decreases with increasing MA inventory in the fuel and confi rms that the addition of MA has a negative effect on the delayed neutron fraction.
    Źródło:
    Nukleonika; 2015, 60, 1; 171-179
    0029-5922
    1508-5791
    Pojawia się w:
    Nukleonika
    Dostawca treści:
    Biblioteka Nauki
    Artykuł
    Tytuł:
    Modelling of thermal hydraulics in a KAROLINA calorimeter for its calibration methodology validation
    Autorzy:
    Luks, A.
    Pytel, K.
    Tarchalski, M.
    Uzunow, N.
    Krok, T.
    Powiązania:
    https://bibliotekanauki.pl/articles/147579.pdf
    Data publikacji:
    2016
    Wydawca:
    Instytut Chemii i Techniki Jądrowej
    Tematy:
    computional fluid dynamics
    CFD
    differential calorimeter
    gamma heating
    gamma rays
    Jules Horowitz Reactor
    JHR
    modelling of thermal hydraulics
    nuclear heating
    nuclear reactor
    research
    reactor MARIA
    Opis:
    Results of numerical calculations of heat exchange in a nuclear heating detector for nuclear reactors are presented in this paper. The gamma radiation is generated in nuclear reactor during fission and radiative capture reactions as well as radioactive decay of its products. A single-cell calorimeter has been designed for application in the MARIA research reactor in the National Centre for Nuclear Research (NCBJ) in Świerk near Warsaw, Poland, and can also be used in the Jules Horowitz Reactor (JHR), which is under construction in the research centre in Cadarache, France. It consists of a cylindrical sample, which is surrounded by a gas layer, contained in a cylindrical housing. Additional calculations had to be performed before its insertion into the reactor. Within this analysis, modern computational fuid dynamics (CFD) methods have been used for assessing important parameters, for example, mean surface temperature, mean volume temperature, and maximum sample (calorimeter core) temperature. Results of an experiment performed at a dedicated out-of-pile calibration bench and results of numerical modelling validation are also included in this paper.
    Źródło:
    Nukleonika; 2016, 61, 4; 453-460
    0029-5922
    1508-5791
    Pojawia się w:
    Nukleonika
    Dostawca treści:
    Biblioteka Nauki
    Artykuł
      Wyświetlanie 1-3 z 3

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