Study on Neutron Sensitivity Calculation Model of Ex-core Neutron Detector
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摘要: 本研究以蒙特卡罗方法为基础，提出了一种中子灵敏度计算模型，用于堆外核探测器核性能设计研究。首先，基于探测器物理原理，得到中子灵敏度的影响因素；在此基础上，分析探测器孔道处中子场特性，提出中子灵敏度计算模型；对计算模型进行讨论得到其不确定度分析。最后对模型展开验证，结果表明计算得到的中子灵敏度与实测数据的误差在可接受范围内，验证了模型的可行性。Abstract: Based on the Monte Carlo method, this thesis proposes a neutron sensitivity calculation model for the design and study of the performance of ex-core neutron detectors. Firstly, based on the physical principle of the detector, the influencing factors of neutron sensitivity are obtained. On this basis, the neutron field characteristics at the monitor holes are analyzed, and the neutron sensitivity calculation model is proposed. The calculation model is discussed to obtain the uncertainty analysis of the model. Finally, the model is verified, and the error between the calculated neutron sensitivity and the measured data is within the acceptable range, which verifies the feasibility of the model.
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图 1 涂硼正比计数管工作原理示意图
n—中子；−HV—负高压；RL—负载电阻；V(t)—阳极丝引出的电压信号
Figure 1. Schematic Diagram of the Principle of Boron-coated Proportional Detector
图 2 涂硼正比计数管位于单向中子场示意图
Figure 2. Schematic Diagram of Boron Coated Proportional Counter in One-way Neutron Field
图 3 探测器所处中子场示意图
Figure 3. Schematic Diagram of the Neutron Field in which the Detector is Located
表 1 涂硼正比计数管相关参数
Table 1. Boron-Coated Proportional Counter Tube Related Parameters
组成部分 物理参数 数值 外筒 直径/mm 80 长度/mm 1400 壁厚/mm 1.5 材料及密度 TA2，4.51 g/cm3 电压/V 0 阴极管 直径/mm 70 长度/mm 1150 壁厚/mm 1.5 材料及密度 TA2，4.51 g/cm3 电压/V 0 阳极丝 直径/μm 30 长度/mm 1150 材料 镀金钨丝 内侧材料 钨丝（半径7.5 μm） 外侧材料 金（内径7.5 μm、外径15 μm） 电压/V 1100 涂硼参数 位置 阴极内侧 材料 90%10B+10%11B 厚度/μm 3.4 工作气体 组分与气压 23.5 kPa Ar + 4 kPa CO2 
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表 2 模型计算结果与实测数据
Table 2. Model Calculation Results and Measured Data
探测器种类 计算结果 实测数据 模型的中子
灵敏度误差/%模型相对不确定度/% 涂硼正比计数管 48.08±10.69 cm2 43.63±2.44 cm2 10.20 24.50 裂变电离室 1.07±0.24 cm2 0.92±0.07 cm2 16.30 26.09 补偿型涂硼电离室 (1.37±0.30)×10−13 A·cm2·s (1.50±0.08)×10−13 A·cm2·s 8.67 20.00
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