Core design of a high breeding fast reactor cooled by supercritical pressure light water

Takayuki Someya, Akifumi Yamaji

    Research output: Contribution to journalArticle

    7 Citations (Scopus)

    Abstract

    A high breeding fast reactor core concept, cooled by supercritical pressure light water has been developed with fully-coupled neutronics and thermal-hydraulics core calculations, which takes into account the influence of core pressure loss to the core neutronics characteristics. Design target of the breeding performance has been determined to be compound system doubling time (CSDT) of less than 50 years, by referring to the relationship of energy consumption and economic growth rate of advanced countries such as the G7 member countries. Based on the past design study of supercritical water cooled fast breeder reactor (Super FBR) with the concept of tightly packed fuel assembly (TPFA), further improvement of breeding performance and reduction of core pressure loss are investigated by considering different fuel rod diameters and coolant channel geometries. The sensitivities of CSDT and the core pressure loss with respect to major core design parameters have been clarified. The developed Super FBR design concept achieves fissile plutonium surviving ratio (FPSR) of 1.028, compound system doubling time (CSDT) of 38 years and pressure loss of 1.02 MPa with positive density reactivity (negative void reactivity). The short CSDT indicates high breeding performance, which may enable installation of the reactors at a rate comparable to energy growth rate of developed countries such as G7 member countries.

    Original languageEnglish
    Pages (from-to)30-37
    Number of pages8
    JournalNuclear Engineering and Design
    Volume296
    DOIs
    Publication statusPublished - 2016 Jan 1

    Fingerprint

    supercritical pressures
    light water
    Fast reactors
    reactors
    breeding
    G-7 country
    Water
    Breeder reactors
    breeder reactors
    water
    Plutonium
    reactivity
    Reactor cores
    plutonium
    reactor design
    reactor cores
    Coolants
    void
    coolants
    energy consumption

    ASJC Scopus subject areas

    • Nuclear Energy and Engineering
    • Mechanical Engineering
    • Safety, Risk, Reliability and Quality
    • Materials Science(all)
    • Nuclear and High Energy Physics
    • Waste Management and Disposal

    Cite this

    Core design of a high breeding fast reactor cooled by supercritical pressure light water. / Someya, Takayuki; Yamaji, Akifumi.

    In: Nuclear Engineering and Design, Vol. 296, 01.01.2016, p. 30-37.

    Research output: Contribution to journalArticle

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