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

Takayuki Someya*, Akifumi Yamaji

*この研究の対応する著者

    研究成果査読

    9 被引用数 (Scopus)

    抄録

    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.

    本文言語English
    ページ(範囲)30-37
    ページ数8
    ジャーナルNuclear Engineering and Design
    296
    DOI
    出版ステータスPublished - 2016 1 1

    ASJC Scopus subject areas

    • 原子力エネルギーおよび原子力工学
    • 機械工学
    • 安全性、リスク、信頼性、品質管理
    • 材料科学(全般)
    • 核物理学および高エネルギー物理学
    • 廃棄物管理と処理

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