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STUDY OF REACTIVITY COEFFICIENTS BASED ON REACTOR TRANSIENT ANALYSIS

STUDY OF REACTIVITY COEFFICIENTS BASED ON REACTOR TRANSIENT ANALYSIS
基于反应堆瞬态分析的反应性系数研究
批准号:
63580180
负责人:
TAKEDA Toshikazu
金额:
$1.02万
依托单位:
依托单位国家:
日本
项目类别:
Grant-in-Aid for General Scientific Research (C)
财政年份:
1988
资助国家:
日本
项目状态:
已结题
起止时间:
1988 至 1989

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中文摘要
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英文摘要
Foi reactor safety, it is necessary to study the transient response of reactor power, coolant temperature, etc. against various causes of accidents. In the present work, we have used a space-time kinetics code to study the effects of reactivity coefficients on some fundamental transient characteristics.First, we have studied the methodology of producing the effective group cross sections. A highly accurate treatment of the self shielding is very important in detailed nuclear characteristics calculations, and we have developed a method of applying the multi-band theory to heterogeneous lattices. The new methodology has been applied to the analysis of a tight-pitch lattice experiment carried out on the Kyoto University Critical Assembly, and the results have been compared with those of the conversational self-shielding factor method and of the Monte Carlo method to see its validity.Next, we have investigated a method for space-time transient analysis. Because of the weak neutronic coupling in large reactors, a reactivity insertion causes a strong local distortion in the neutron flux distribution, which makes it necessary to develop an efficient three-dimensional method. We have newly formulated the neutron currents in the framework of time-dependent diffusion theory, and developed a coarse-mesh, but very accurate, method of transient analysis. The method has been applied to a fast breeder reactor to estimate the coarse-mesh effect on the transient power distributions and sodium temperature distributions.Finally, we have summarized the problems deferred to a future work.
期刊论文(23)
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会议论文
T. Takeda, A. Yoshimura, T. Kamei, and K. Shirakata: "Prediction uncertainty evaluation methods of core performance parameters in large liquidmetal fast breeder reactors" Nuclear Science and Engineering. 103. 157 (1989)
T. Takeda、A. Yoshimura、T. Kamei、K. Shirakata:“大型液态金属快中子增殖堆堆芯性能参数的预测不确定性评估方法”核科学与工程。
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T.Nishigori,;T.Takeda,;T.Sekiya.: Journal of Nuclear Science and Technology. 25. 943-947 (1988)
T.Nishigori,;T.Takeda,;T.Sekiya.:核科学与技术杂志。
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T.Takeda: "Improvement of A ThreeーDimensional Transport Code and Its Application to Core Analyus of Large LMFBRs." International Conference an the Physics of Reactors:Operation,Design and Compatation Marsectle Frame,Aprul23ー27,1990. (1990)
T.Takeda:“三维输运代码的改进及其在大型 LMFBR 堆芯分析中的应用。”反应堆物理国际会议:操作、设计和 Compatation Marsectle 框架,1990 年 4 月 23-27 日。(1990 年)
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23
    A safety research on nuclear reactors based on the microscopic reactor physics
    • 批准号:
      16360475
    • 项目类别:
      Grant-in-Aid for Scientific Research (B)
    • 资助金额:
      $6.59万
    • 财政年份:
      2004
    • 负责人:
      TAKEDA Toshikazu
    • 依托单位:
    Study on Micro Reactor Physics for Improvement of Neutronics Calculation
    • 批准号:
      13480148
    • 项目类别:
      Grant-in-Aid for Scientific Research (B)
    • 资助金额:
      $6.34万
    • 财政年份:
      2001
    • 负责人:
      TAKEDA Toshikazu
    • 依托单位: