自給自足型トリウム熔融塩炉の特性 Characteristics of Thorium Molten-Salt Reactor with Self-Sustainability

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  In this paper, the burn-up characteristics of a 200 MW<sub>e</sub> molten-salt reactor are studied. This reactor has a three-region core in order to reduce the peak in fast neutron flux distribution. The reactor is operated for 30 years with the load factor of 0.75. The fuel is fed to the reactor every 33 days. The chemical processing of the fuel salt is performed every 7.5 years. Based on calculations using the nuclear analysis code SRAC2006 and the burn-up analysis code ORIGEN2, the following results have been obtained. (1) The graphite moderators can be used throughout the reactor lifetime without replacement. (2) The reactor is self-sustainable having an average fuel conversion ratio of 1.01. (3) The initial inventory of <sup>233</sup>U is 1.13 t, net feed in 30 years is 0.34 t; thus, the necessary amount of <sup>233</sup>U is 1.48 t. (4) Pu isotopes are produced at 1.5 kg and minor actinides at 27 kg per 1 GWe output in 30 years, which are absolutely small compared with those produced by BWR.<br>

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  • 日本原子力学会和文論文誌 = Transactions of the Atomic Energy Society of Japan

    日本原子力学会和文論文誌 = Transactions of the Atomic Energy Society of Japan 7(2), 127-133, 2008-06-01

    Atomic Energy Society of Japan

参考文献:  18件中 1-18件 を表示

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各種コード

  • NII論文ID(NAID)
    10020753296
  • NII書誌ID(NCID)
    AA11643165
  • 本文言語コード
    JPN
  • 資料種別
    ART
  • ISSN
    13472879
  • NDL 記事登録ID
    9532493
  • NDL 雑誌分類
    ZN36(科学技術--原子力工学・工業)
  • NDL 請求記号
    Z74-C788
  • データ提供元
    CJP書誌  CJP引用  NDL  J-STAGE 
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