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Performance of large neutron detectors containing Lithium-Gadolinium-Borate scintillator

机译:含锂 - 钆 - 硼酸锂闪烁体的大中子探测器的性能

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This paper describes the development and testing of a neutron counter, spectrometer, and dosimeter that is compact, efficient, and accurate. A self-contained neutron detection instrument has wide applications in health physics, scientific research, and programs to detect, monitor, and control strategic nuclear materials (SNM). The 1.3 liter detector head for this instrument is a composite detector with an organic scintillator containing uniformly distributed 6Li6natGd10B3O9:Ce (LGB:Ce) microcrystals. The plastic scintillator acts to slow impinging neutrons and emits light proportional to the energy lost by the neutrons as they moderate in the detector body. Moderating neutrons that have slowed sufficiently capture in one of the Lithium-6, Boron-10, or Gadolinium-157 atoms in the LGB:Ce scintillator, which then releases the capture energy in a characteristic cerium emission pulse. The measured captured pulses indicate the presence of neutrons. When a scintillating fluor is present in the plastic, the light pulse resulting from the neutron moderating in the plastic is paired with the LGB:Ce capture pulse to identify the energy of the neutron. About 2% of the impinging neutrons lose all of their energy in a single collision with the detector. There is a linear relationship between the pulse areas of this group of neutrons and energy. The other 98% of neutrons have a wide range of collision histories within the detector body. When these neutrons are "binned" into energy groups, each group contains a distribution of pulse areas. This data was used to assist in the unfolding of the neutron spectra. The unfolded spectra were then validated with known spectra, at both neutron emitting isotopes and fission/accelerator facilities. Having validated spectra, the dose equivalent and dose rate are determined by applying standard, regulatory damage coefficients to the measured neutron counts for each energy bin of the spectra. Testing at the Los Alamos Neutron Science Center (LAN- CE), Edwards Accelerator Laboratory (EAL) at Ohio University and the Radiation Center at University of Massachusetts-Lowell has demonstrated that the instrument can measure neutrons and their spectra over the range between 0.8 MeV and 150 MeV with an uncertainty of only +/??? 8%. An independent test of the LGB:Ce neutron spectrometer was conducted by a US Defense Threat Reduction Agency (DTRA) team at the Idaho National Laboratory (INL). The results of this evaluation showed that the neutron spectrometer accurately identified bare radioactive isotopes by their spectra. Further, masking and shielding materials alter those spectra in predictable ways that permit an extrapolation from the observed spectra back to the identity of the isotopic spectrum.
机译:本文介绍了紧凑,高效,准确的中子计数器,光谱仪和剂量计的开发和测试。一种独立的中子检测仪在卫生理理,科学研究和检测,监测和控制战略核材料(SNM)方案中具有广泛的应用。所述1.3升探测器头,用于该仪器是用含有均匀分布6Li6natGd10B3O9有机闪烁体的复合检测器:Ce的(LGB:Ce)的微晶。塑料闪烁体采用慢撞击中子,并在探测器主体中温和时发出与中子损失的能量成比例的光。在LGB中的锂-6,硼-10或钆-157原子之一中缓慢捕获的调节中子:Ce闪烁体,然后在特征铈发射脉冲中释放捕获能量。测量的捕获脉冲表示存在中子。当在塑料中存在闪烁的氟时,塑料中中子温度温度导致的光脉冲与LGB:Ce捕获脉冲配对以识别中子的能量。大约2%的撞击中子在与探测器碰撞中失去了所有能量。该组中子和能量的脉冲区域之间存在线性关系。其他98%的中子在探测器体内具有各种碰撞历史。当这些中子“箱子”进入能量组时,每组含有脉冲区域的分布。该数据用于帮助中子谱的展开。然后用已知的光谱验证展开的光谱,在中子发射同位素和裂变/加速器设施中。具有验证的光谱,剂量当量和剂量率通过施加标准,调节损伤系数来确定光谱的每个能量箱的测量中子计数。在洛斯阿拉莫斯中子科学中心(LAN-CE)测试,爱德华兹加速器实验室(EAL)在俄亥俄大学和辐射中心在马萨诸塞州洛厄尔大学已经证明,该仪器可以测量中子和它们的光谱在范围0.8兆电子伏之间和150 mev只有+ / ???的不确定性8%。 LGB的独立测试:CE中子谱仪由爱达荷州国家实验室(INL)的美国国防威胁减少机构(DTRA)团队进行。该评估结果表明,中子谱仪精确地通过其光谱识别裸放射性同位素。此外,掩模和屏蔽材料以可预测的方式改变这些光谱,其允许观察到的光谱从观察到的光谱返回到同位素光谱的身份。

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