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

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Abstract

  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>

Journal

  • Transactions of the Atomic Energy Society of Japan

    Transactions of the Atomic Energy Society of Japan 7(2), 127-133, 2008-06-01

    Atomic Energy Society of Japan

References:  18

Cited by:  1

Codes

  • NII Article ID (NAID)
    10020753296
  • NII NACSIS-CAT ID (NCID)
    AA11643165
  • Text Lang
    JPN
  • Article Type
    Journal Article
  • ISSN
    13472879
  • NDL Article ID
    9532493
  • NDL Source Classification
    ZN36(科学技術--原子力工学・工業)
  • NDL Call No.
    Z74-C788
  • Data Source
    CJP  CJPref  NDL  J-STAGE 
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