The capability of SN methodology to accurately predict the neutronics behavior of a compact, light water‐moderated reactor is examined. This includes examining the effects of cross‐section modeling and the choice of spatial and angular representation. The isothermal temperature coefficient in the range of 293 K to 355 K is analyzed, as well as the radial fission density profile across the central fuel element. Measured data from a series of critical experiments are used for these analyses.


    Zugriff

    Zugriff prüfen

    Verfügbarkeit in meiner Bibliothek prüfen

    Bestellung bei Subito €


    Exportieren, teilen und zitieren



    Titel :

    SN transport analyses of critical reactor experiments for the SNTP program


    Beteiligte:
    Mays, Claude W. (Autor:in) / El-Genk, Mohamed S. (Herausgeber:in) / Hoover, Mark D. (Herausgeber:in)

    Kongress:

    10th SymposiumùSpace Nuclear Power and Propulsion ; 1993 ; Albuquerque, NM, USA


    Erschienen in:

    AIP Conference Proceedings ; 271 , 2 ; 811-815


    Erscheinungsdatum :

    15.01.1993


    Format / Umfang :

    5 pages





    Medientyp :

    Aufsatz (Konferenz)


    Format :

    Elektronische Ressource


    Sprache :

    Englisch




    SNTP program reactor design

    WALTON, LEWIS / SAPYTA, JOSEPH | AIAA | 1993


    Sntp Propellant Management System

    T. Tippetts | NTIS | 1993


    SNTP environmental, safety, and health

    Harmon, Charles D. | NTRS | 1993


    SN Transport Analyses of Critical Reactor Experiments for the SNTP Program

    Mays, C. W. / American Institute of Physics | British Library Conference Proceedings | 1993


    Description of the Space Nuclear Thermal Propulsion (SNTP) cryogenic and hot‐hydrogen test facility

    Thompson, David A. / Riffle, George K. / Merdich, Jeff A. | American Institute of Physics | 1993