黄饼材料中铀的准确定量是后续处理工艺选择的关键,文中在主动式多重性方法的基础上,提出了一种通过记录分析中子源诱发238U裂变信息,进行铀定量的方法。但由于黄饼材料自身存在中子自屏蔽效应以及含水量的差异,导致定量结果存在偏差。...黄饼材料中铀的准确定量是后续处理工艺选择的关键,文中在主动式多重性方法的基础上,提出了一种通过记录分析中子源诱发238U裂变信息,进行铀定量的方法。但由于黄饼材料自身存在中子自屏蔽效应以及含水量的差异,导致定量结果存在偏差。为了进一步提高定量准确性,使用MCNP(Monte Carlo N-Particle Transport)结合MATLAB程序优化选择了241Am-Be源作为激发源;另外,通过对不同质量及含水量系列化样品的模拟发现:铀定量误差主要来自于泄漏增殖因子ML与增殖因子M差距的不匹配。通过MCNP模拟获取M随铀质量变化规律的曲线后,根据样品净含量选择合适的增殖因子M,再根据二重计数率D进行定量计算,获得铀定量的相对误差小于5%;含水量的变化带来的中子自屏蔽效应对多重计数率影响较大,通过S0/Si与D0/Di的关系对二重计数率D进行修正后再进行计算,铀定量的相对误差能够控制在10%左右;该研究对中子多重性方法在黄饼生产与测量中的应用推广具有重要的参考价值。展开更多
Accurate neutron flux values in irradiation channels of research reactors are very essential to their usage. The total neutron flux of the Ghana Research Reactor-1(GHARR-1) was measured after a beryllium reflector was...Accurate neutron flux values in irradiation channels of research reactors are very essential to their usage. The total neutron flux of the Ghana Research Reactor-1(GHARR-1) was measured after a beryllium reflector was added to its shim to compensate for excess reactivity loss. The thermal, epithermal and fast neutron fluxes were determined by the method of foil activation. The experimental samples with and without a cadmium cover of 1-mm thickness were irradiated in the isotropic neutron field of the irradiation sites of Ghana Research Reactor-1 facility. The induced activities in the sample were measured by gamma ray spectrometry with a high purity germanium detector. The necessary correction for gamma attenuation, thermal neutrons and resonance neutron self-shielding effects were taken into account during the experimental analysis. By defining cadmium cutoff energy of 0.55eV, Al-0.1% Au wires of negligible thickness were irradiated at 3kW to determine the neutron fluxes of two irradiation channels, outer channel 7 and inner channel 2 whose Neutron Shaping Factor (α) were found to be (0.037 ± 0.001) and (–0.961 ± 0.034). The neutron flux ratios at the inner irradiation site 2 were found to be, (25.308 ± 3.201) for thermal to epithermal neutrons flux, (0.179 ± 0.021) for epithermal to fast neutrons flux and (4.528 ± 0.524) for thermal to fast neutrons flux, in the outer irradiation site 7, the neutron flux ratios were found to be, (40.865 ± 3.622) for thermal to epithermal neutrons flux, (0.286 ± 0.025) for epithermal to fast neutrons flux and (11.680 ± 1.030) for thermal to fast neutrons flux.展开更多
文摘黄饼材料中铀的准确定量是后续处理工艺选择的关键,文中在主动式多重性方法的基础上,提出了一种通过记录分析中子源诱发238U裂变信息,进行铀定量的方法。但由于黄饼材料自身存在中子自屏蔽效应以及含水量的差异,导致定量结果存在偏差。为了进一步提高定量准确性,使用MCNP(Monte Carlo N-Particle Transport)结合MATLAB程序优化选择了241Am-Be源作为激发源;另外,通过对不同质量及含水量系列化样品的模拟发现:铀定量误差主要来自于泄漏增殖因子ML与增殖因子M差距的不匹配。通过MCNP模拟获取M随铀质量变化规律的曲线后,根据样品净含量选择合适的增殖因子M,再根据二重计数率D进行定量计算,获得铀定量的相对误差小于5%;含水量的变化带来的中子自屏蔽效应对多重计数率影响较大,通过S0/Si与D0/Di的关系对二重计数率D进行修正后再进行计算,铀定量的相对误差能够控制在10%左右;该研究对中子多重性方法在黄饼生产与测量中的应用推广具有重要的参考价值。
文摘Accurate neutron flux values in irradiation channels of research reactors are very essential to their usage. The total neutron flux of the Ghana Research Reactor-1(GHARR-1) was measured after a beryllium reflector was added to its shim to compensate for excess reactivity loss. The thermal, epithermal and fast neutron fluxes were determined by the method of foil activation. The experimental samples with and without a cadmium cover of 1-mm thickness were irradiated in the isotropic neutron field of the irradiation sites of Ghana Research Reactor-1 facility. The induced activities in the sample were measured by gamma ray spectrometry with a high purity germanium detector. The necessary correction for gamma attenuation, thermal neutrons and resonance neutron self-shielding effects were taken into account during the experimental analysis. By defining cadmium cutoff energy of 0.55eV, Al-0.1% Au wires of negligible thickness were irradiated at 3kW to determine the neutron fluxes of two irradiation channels, outer channel 7 and inner channel 2 whose Neutron Shaping Factor (α) were found to be (0.037 ± 0.001) and (–0.961 ± 0.034). The neutron flux ratios at the inner irradiation site 2 were found to be, (25.308 ± 3.201) for thermal to epithermal neutrons flux, (0.179 ± 0.021) for epithermal to fast neutrons flux and (4.528 ± 0.524) for thermal to fast neutrons flux, in the outer irradiation site 7, the neutron flux ratios were found to be, (40.865 ± 3.622) for thermal to epithermal neutrons flux, (0.286 ± 0.025) for epithermal to fast neutrons flux and (11.680 ± 1.030) for thermal to fast neutrons flux.
