微型反应堆照射座内热中子通量谱的测定

DETERMINATION OF THERMAL NEUTRON FLUX SPECTRUM AT THE IRRADIATION SITES OF MNSR

  • 摘要: <正> 一、基本原理 用一组展开函数?_i(E)来表示所测的真实谱φ(E),典型的展开函数是一组N—1项的多项式,N是探测箔种类数。

     

    Abstract: It is very important to determine the thermal neutron flux spectrum at theirradiation sites of the MNSR. Five activation detectors ~(164)Dy, ~(151)Eu, ~(176)Lu, ~(151)In,~(197)Au are used in this work, and thermal neutron flux spectrum in the thermalcolumn of SPR reactor is used as a reference spectrum. The ratio of the detectedactivities in MNSR and the detected activities in SPR are determined, the developedspectrum in MNSR is obtained. The parameters of the spectrum are calculated andcompared with experimental data. The results are satisfactory.

     

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