Calculation of Lead Shielding in Relative Distribution Measurement Systems of Neutron Flux in Reactors
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摘要: 为批量化测量探测片活性,设计了多道中子注量率相对分布测量系统。每一个NaI探测器测量一个探测片,探测器之间采用铅屏蔽。为了消除其他通道探测片对本通道探测片测量结果的影响,通过设计保证邻近通道活化探测片对本通道干扰小于0.05%。本文采用点源积分方法计算(经蒙特卡罗模拟验证),并确定了满足屏蔽要求的铅屏蔽体尺寸。Abstract: The measurement system for relative distribution of multichannel neutron flux is designed to massively measure the radioactivity of irradiated foils.Every NaI detector measures one irradiated foil and the lead shield is used in detectors.To eliminate the effect of foils from other tracks on the measurement result of foil detector in its own track,this paper designs that the interference from the irradiated foils at the adjacent tracks on the measured tracks is less than 0.05%.This paper confirms the size of lead shield which meets the shield requirements by using the calculation method of point source integral and Monte Carlo verification method.
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Key words:
- Neutron flux /
- Irradiated foil /
- Lead /
- Shield calculation
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