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Design and simulation of neutron radiography system based on ~(241)Am-Be source

机译:基于〜(241)Am-Be源的中子照相系统的设计与仿真

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摘要

Neutron imaging is extended rapidly as a means of non-destructive testing (NDT) of materials. Various effective parameters on the image quality are needed to be studied for neutron radiography system with good resolution. In the present study a portable system of neutron radiography has been designed using ~(241)Am-Be neutron source. The effective collimator parameters were calculated to obtain relatively pure, collimated and uniform neutron beam. All simulations were carried out in two stages using MCNPX Monte Carlo code. In the first stage, different collimator configurations were investigated and the appropriate design was selected based on maximum intensity and uniformity of neutron flux at the Image plane in the outlet of collimator. Then, the overall system including source, collimator and sample was simulated for achieving radiographic images of standard samples. Normalized thermal neutron fluence of 2.61 x 10~(-5)cm~(-2) per source particle with n/γ ratio of 1.92 x 10~5cm~(-5) μSv~(-1) could be obtained at beam port of the designed collimator. Quality of images was assessed for two standard samples, using radiographic Imaging capability in MCNPX. The collimated neutron beam in the designed system could be useful In a transportable exposure module for neutron radiography application.
机译:作为材料的无损检测(NDT)手段,中子成像技术得到了快速扩展。对于具有良好分辨率的中子射线照相系统,需要研究关于图像质量的各种有效参数。在本研究中,已经设计了一种使用〜(241)Am-Be中子源的便携式中子射线照相系统。计算有效的准直仪参数以获得相对纯净,准直且均匀的中子束。使用MCNPX蒙特卡洛代码在两个阶段中进行了所有模拟。在第一阶段,研究了不同的准直仪配置,并根据最大强度和准直仪出口图像平面上中子通量的均匀性选择了合适的设计。然后,模拟整个系统,包括光源,准直仪和样品,以获取标准样品的射线照相图像。在束口处可获得每个源粒子2.61 x 10〜(-5)cm〜(-2)的归一化热中子通量,n /γ比为1.92 x 10〜5cm〜(-5)μSv〜(-1)。设计的准直器。使用MCNPX中的射线照相成像功能评估了两个标准样品的图像质量。设计的系统中准直的中子束在中子射线照相应用的可移动曝光模块中可能有用。

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