摘要
设计了一种多路准直器用于消除中子照相中的散射中子,利用MCNP5对准直器的中子吸收材料、长度进行了优化设计,利用该准直器对不同厚度的水层样品在不同样品探测器距离下进行了中子照相的MC模拟计算。计算结果表明选用25μm的Gd作为准直器的中子吸收涂层,准直器长度为1cm时可消除98%的散射中子,使用该准直器可以有效提高中子照相定量分析的精度。
A muhichannel collimator for neutron radiography has been designed to remove the scattered neu- trons. The optimization design of the coating and the length of collimator have been done by MCNP5 which is a Monte Carlo code. Some neutron radiographies with different sample thickness in different sample to detector distance have been simulated. The calculation shows that 98% scattered neutrons have been removed by the multichannel collimator with the length of 1 cm and the Gd coating of 25 μm. The precision of the quantitative neutron radiography has been substantially improved.
出处
《核电子学与探测技术》
CAS
北大核心
2016年第10期1008-1011,1036,共5页
Nuclear Electronics & Detection Technology
基金
核技术应用教育部工程研究中心开放基金(HJSJYB 2015-1)资助
关键词
中子照相
多路准直器
定量分析
散射中子
蒙特卡罗
neutron radiography
multichannel collimator
quantitative analysis
scattered neutrons
Monte Carlo
