Choice of unified optimal radial dimensions for thermionic fuel elements (TFE) is considered for the use of TFE with five‐layer collector assembly in in‐core thermionic reactors (ITR) on thermal and fast neutrons of space nuclear power systems (SNPS) with long (no less 5 years) lifetime and ITR electric power in the range from 30 to 300 kW. A series of optimum conditions has considered taking into account ITR core volume, given values for area of ITR emission surface and ItR effective multiplication factor, characteristics of core structure (average moderator portion in core of ITR on thermal neutrons, fuel pin porosity, coolant portion in core and so on), TFE hookup in thermionic generator and so on.

    On the base of analysis of these conditions the conclusion has made that in aforesaid range of ITR electric power the TFE optimal radial dimensions unified for use in ITR on both thermal and fast neutrons is in the range: TFE external diameter is from 22 to 25 mm, fuel diameter from 15, 5 to 17,5 mm. Under greater electric power the to lesser radial dimensions is expedient.


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    Titel :

    Optimal dimensions of thermionic fuel elements for in‐core thermionic reactors


    Beteiligte:
    Andreev, Pavel V. (Autor:in) / Galkin, Anatoly Ya. (Autor:in) / Zhabotinsky, Evgeny E. (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 , 3 ; 1529-1534


    Erscheinungsdatum :

    20.01.1993


    Format / Umfang :

    6 pages





    Medientyp :

    Aufsatz (Konferenz)


    Format :

    Elektronische Ressource


    Sprache :

    Englisch




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