利用缓发中子法测量235U裂变数的实验研究

Experimental Study on Determination of 235U Fission Number With Delayed Neutron Detection Method

  • 摘要: 缓发中子伴随核裂变产生,通过对它的测量估算核裂变数是一需实验检验的新方法。在中国原子能科学研究院微堆辐照235U样品,采用3He正比计数器测量缓发中子,并通过缓发中子数反推得到铀样品的总裂变数。利用高纯锗γ谱仪测量被辐照样品发射的缓发γ射线,通过缓发γ射线数得到样品总裂变数。对两种测量方法得到的结果进行了对比和分析,结果表明,用缓发中子法和缓发γ法对同一样品测量的结果一致,缓发中子法可作为一种辅助诊断方法。

     

    Abstract: The delayed neutron is emitted after one fission product generated. A new method evaluating fission number by the measurement of delayed neutron number is needed to be verified by experiment. 235U samples were irradiated with MNPR at CIAE, the delayed neutrons were measured with 3He proportional detector and the fission number was determined. The result was verified by delayed γ method. The delayed neutron method is a supplementary way for delayed γ method.

     

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