Design Concept of Fast Spectrum Pulse Reactor with Packed Core of Coated Dilute Fuel Particles

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A fast neutron pulse reactor that can provide high neutron fluence with relatively short pulse half-width is proposed, which has a core constituted of uranium or plutonium nitride diluted with titanium nitride, formed into particles coated with titanium nitride and packed without moderator. Dilution of the fuel kernel is shown to enhance the neutron fluence obtainable within the allowable maximum fuel temperature. Titanium nitride possesses high heat capacity, which also enables large neutron fluence before attainment of the allowable maximum fuel temperature. As fuel, <SUP>233</SUP>U and <SUP>239</SUP>Pu have the advantage over <SUP>235</SUP>U of permitting criticality to be attained with lower fuel enrichment. The maximum fluence obtainable with a fuel composition of <SUP>239</SUP>Pu enriched to 0.6 and diluted to 0.11 (<SUP>239</SUP>PuN+<SUP>238</SUP>UN)/(<SUP>239</SUP>PuN+<SUP>238</SUP>UN+TiN) volume is 3×10<SUP>16</SUP>n/cm<SUP>2</SUP>, which is 50 times what has been indicated for a conventional fast pulse reactor. The pulse width is significantly longer than that of the above-mentioned conventional reactor, but if necessary it can be shortened down to roughly equal value by adopting non-diluted fuel, at the expense of only reducing by half the obtainable neutron fluence.

収録刊行物

  • Journal of nuclear science and technology  

    Journal of nuclear science and technology 33(7), p.547-554, 1996-07-25 

    Atomic Energy Society of Japan

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各種コード

  • NII論文ID(NAID)
    10002075077
  • NII書誌ID(NCID)
    AA00703720
  • 本文言語コード
    ENG
  • 資料種別
    ART
  • ISSN
    00223131
  • NDL 記事登録ID
    4060405
  • NDL 雑誌分類
    ZM35(科学技術--物理学)
  • NDL 請求記号
    Z53-A460
  • データ提供元
    CJP書誌  NDL  J-STAGE 
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