Design and Safety Aspect of Lead and Lead-Bismuth Cooled Long-Life Small Safe Fast Reactors for Various Core Configurations

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著者

    • SU'UD Zaki
    • Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology
    • SEKIMOTO Hiroshi
    • Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology

抄録

Design and safety aspects of long-life small safe fast reactors using liquid lead or leadbismuth coolant with metallic or nitride fuel are discussed. Neutronic analyses are performedto investigate the effect of core height to diameter ratio (H/D) on design performance of theproposed reactors. All reactors are subjected to the constraint of 12 years operation withoutrefueling and shuffling with constant 150MWt reactor power and also to the requirement of maximum excess reactivity during burnup to be less than 0.1%Δk. The results show that the pancake design with H/D of -2/3 gives the most negative coolant void coefficient under the requirements for excess reactivity. Modified designs with the central region axially fulfilled with fertile material are proposed to improve the coolant void coefficient. Ther al-hydraulicanalysis results show the possibility to operate the reactors up to the end of life without changing their orifice pattern, necessary pumping power for the proposed design smaller than the conventional large sodium cooled FBR, and the natural circulation contribution of 25-40% at the normal operating condition. The reactivity feedback coefficients are also estimated andappeared to be negative for all the components including the coolant density coefficient.

収録刊行物

  • Journal of nuclear science and technology  

    Journal of nuclear science and technology 32(9), 834-845, 1995-09-25 

    Atomic Energy Society of Japan

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各種コード

  • NII論文ID(NAID)
    10002073079
  • NII書誌ID(NCID)
    AA00703720
  • 本文言語コード
    ENG
  • 資料種別
    ART
  • ISSN
    00223131
  • データ提供元
    CJP書誌  CJP引用  J-STAGE 
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