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 ${}^1$H($n_{th}$, $\gamma$)${}^2$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.

使用 MCNPX 代码（2.6.0 版，带有 ENDF/B-VII 横截面库（ENDF，2011）设计并模拟了具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） ））。所提出的系统旨在提供基于对 2.22 MeV 伽马射线的探测的热中子图${}^1$H（$n_{吨H}$,$\gamma$)${}^2$D反应。在目前的工作中，使用蒙特卡洛代码 FLUKA 及其闪烁光传输能力，进行了几项重要的升级，包括塑料闪烁体响应中的光传输建模、分析串扰现象、优化系统几何形状，以及为热中子图像重建提供了一种新方法。结果表明，后两种情况在改善热中子通量纵向剖面方面发挥了重要作用。