核素中子源发射率绝对测量装置参数研究及实验验证

Research And Experimental Verification of Absolute Measurement Facility Parameters for Radionuclide Neutron Source Emission Rate

  • 摘要: 锰浴活化法是普遍采用的一种中子源发射率定值方法,本研究采用蒙特卡罗方法(MCNP)计算锰浴装置中溶液池半径、MnSO4溶液密度和测量室体积等主要参数对中子俘获份额、泄漏份额和探测器计数率的影响,并计算不同尺寸溶液池和测量室的情况下,测量中子源发射率时的活化计数率。依据模拟计算的结果建立一套可移动式小锰浴装置,结果表明,在测量241Am-Be源时净计数率比原有锰浴标准装置提高了约11.5倍,测量范围扩大约1个数量级。采用可移动式小锰浴装置测量两枚低发射率中子源,发射率分别为4.09×104 s−1和1.75×105 s−1,相对合成标准不确定度小于1.5%(k=1)。

     

    Abstract: The manganese bath method is a commonly used method for determining neutron source emission rate.The Monte Carlo method (MCNP) was used to calculate the influence of main parameters such as bath radius, MnSO4 solution density, and measurement chamber volume on neutron capture fraction, leakage fraction, and detector count rate in a manganese bath facility. The activation count rate for measuring neutron source emission rate was also calculated for different sizes of bath and measurement chamber. Based on the calculation results, a movable manganese bath facility was established, which achieved a counting rate approximately 11.5 times higher than the primary manganese bath facility when measuring 241Am-Be neutron source, therefore the measurement range was expanded by approximately one order of magnitude. Two low emission rate neutron sources were measured by movable manganese bath facility, which emission rate is 4.09×104 s−1 and 1.75×105 s−1, respectively. The standard uncertainty is less than 1.5%.

     

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