Abstract

The characteristics of the radiation field around a consolidated interim spent nuclear fuel storage facility were investigated comprehensively through Monte Carlo simulations. Neutron and gamma-ray flux/dose contributions from multiple transport pathways, including direct, streaming, skyshine, groundshine, and multishine, were isolated using a modified version of the method that was originally developed by Oh et al. [J. Korean Phys. Soc., Vol. 69, 1057 (2016)] for the evaluation of neutron skyshine from a high-energy electron accelerator. The application of the methodology was demonstrated in this paper, and the flux/dose contributions of individual pathways were examined and compared. The results provided additional insight into how the radiation propagated from the source to off-site locations. The modified method for separating five transport pathways can provide valuable information for shielding optimization during the design phase and is generally applicable to Monte Carlo shielding analyses of other nuclear facilities.

摘要

通过蒙特卡罗模拟全面研究了综合临时乏核燃料储存设施周围的辐射场特性。使用最初由 Oh 等人开发的方法的修改版本分离了来自多个传输路径（包括直接、流、天照、地照和多照）的中子和伽马射线通量/剂量贡献。[J。韩国物理 社会，卷。69, 1057 (2016)] 用于评估来自高能电子加速器的中子天照。本文展示了该方法的应用，并对各个途径的通量/剂量贡献进行了检查和比较。结果提供了关于辐射如何从源传播到场外位置的更多见解。