放射性废物容器的伽马辐射剂量率评估

IF 2.1 Q3 ENGINEERING, ENVIRONMENTAL
A. Ksenofontov, D. Savin
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引用次数: 0

摘要

在放射性废物贮存设施的安全评估中,对人员在贮存设施内进行的各种操作的暴露进行评估被视为一项重要任务。然而,在评估人员照射剂量时,往往不考虑从放射性废物储存设施房舍内的结构中散射出来的辐射。在一些研究中,计算了RW容器的辐射场特性。例如,利用专门的软件,根据一些工程方法和蒙特卡罗方法计算了辐射场。本文主要讨论了位于放射性核废料储存设施内的体积圆柱形源的伽马辐射剂量率的蒙特卡罗计算。本研究评估了储存库的墙壁、地板和天花板的散射辐射对吸收剂量的贡献,同时也考虑了地板被淹的情况。本文将计算的辐射剂量率与不考虑散射辐射的轴对称几何源体积积分计算的辐射剂量率进行了比较。计算表明,如果不考虑储存设施所有墙壁、地板和天花板结构的散射辐射,则剂量率可能被低估多达两倍,这取决于与源的距离。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Assessment of Gamma Radiation Dose Rate from a Container with Radioactive Waste
Assessment of personnel exposure from various operations performed inside radioactive waste (RW) storage facilities is seen as an essential task under the safety assessment of such storage facilities. However, radiation scattered from the structures inside the premises of RW storage facilities is often not taken into account in the assessment of personnel exposure doses. Characteristics of the radiation field from RW containers have been calculated under a few studies. For example, the radiation fields were calculated based on some engineering approaches and the Monte Carlo method using specialized software. This paper focuses on the Monte Carlo calculations of the gamma radiation dose rate from a volumetric cylindrical source located in a RW storage facility. The study evaluates the contributions of scattered radiation from the walls, floor and ceiling of a storage premise to the absorbed dose also considering the case of a flooded floor. The paper compares the calculated radiation dose rates with those evaluated by integrating the source volume for axisymmetric geometries with no account taken of scattered radiation. The calculations show that depending on the distance from the source if no scattered radiation from all the wall, floor and ceiling structures of a storage facility is accounted for, the dose rate may be underestimated by up to two times.
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来源期刊
CiteScore
5.40
自引率
7.40%
发文量
80
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