Department of Physics, Faculty of Sciences, University of Birjand, P.O. Box 97175-615, Birjand, Iran.
Department of Physics, Faculty of Science, Ferdowsi University of Mashhad, P.O. Box 91775-1436, Mashhad, Iran.
Appl Radiat Isot. 2021 Oct;176:109755. doi: 10.1016/j.apradiso.2021.109755. Epub 2021 Jun 24.
A thermal neutron flux measurement tool with two perpendicular sets of plastic scintillator arrays was designed and simulated (Ghal-Eh and Green, 2016) with the MCNPX code (Version 2.6.0, with ENDF/B-VII cross section library (ENDF, 2011)). The proposed system aimed to provide a thermal neutron map based on the detection of 2.22 MeV gamma-rays resulting from H(n, γ)D reactions. In the present work, using Monte Carlo code FLUKA and its scintillation light transport capability, several important upgrades were carried out to include the light transport modeling in the response of plastic scintillators, analyze the cross-talk phenomenon, optimize the system geometry, and also provide a new approach in thermal neutron image reconstruction. The results showed that the last two cases played a significant role in improving the longitudinal profile of thermal neutron flux.
设计并模拟了一种带有两组垂直塑料闪烁体阵列的热中子通量测量工具(Ghal-Eh 和 Green,2016),使用的是 MCNPX 代码(版本 2.6.0,采用 ENDF/B-VII 截面库(ENDF,2011))。该系统旨在基于检测 H(n,γ)D 反应产生的 2.22 MeV 伽马射线,提供热中子图。在本工作中,使用蒙特卡罗代码 FLUKA 及其闪烁光传输能力,进行了几项重要的升级,包括在塑料闪烁体的响应中包含光传输建模、分析串扰现象、优化系统几何形状,并提供了一种新的热中子图像重建方法。结果表明,后两种情况在改善热中子通量的纵向分布方面发挥了重要作用。