Abstract This study assessed the ability of glass ceramics that included zirconolite and barite to protect against different kinds of radiation. Firstly, the mass attenuation coefficient (μ/ρ) values of five different glass ceramics with different amounts of SO3, barite, and zirconolite additive were simulated by MCNPX (version 2.6.0) codes at 0.015–20 MeV photon energies. The simulated results were tested by comparing with theoretical data. With the help of μ/ρ values, essential gamma protection parameters of glass ceramics such as half-value layer, linear attenuation coefficient, effective atomic number, equivalent atomic number, and exposure buildup factor were obtained. The results showed that the S0 sample may be a safe protective material against gamma-radiation. Removal cross-sections of glass ceramics were acquired to determine the capacity of the glass ceramics to stop fast neutrons. The addition of barite and zirconolite raised the density and increased the neutron preventive capacity of the glass ceramics. Finally, the competence of glass ceramics to stop charged alpha and proton particles was investigated using parameters of mass stopping power and projected range. It is concluded that the range of charged particles was the shortest in S0 glass ceramic. The corollaries of the present work will help in determining the impact of barite and zirconolite on the nuclear shielding capacity of glass ceramics.

中文翻译：

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使用硼硅酸钡玻璃陶瓷进行核辐射屏蔽

摘要 本研究评估了包含锆英石和重晶石的玻璃陶瓷抵御不同类型辐射的能力。首先，通过 MCNPX（2.6.0 版）代码在 0.015-20 MeV 光子能量下模拟了具有不同 SO3、重晶石和锆英石添加剂的五种不同玻璃陶瓷的质量衰减系数 (μ/ρ) 值。仿真结果与理论数据进行了对比验证。借助μ/ρ值，获得了玻璃陶瓷的基本伽马保护参数，如半值层、线性衰减系数、有效原子序数、等效原子序数和曝光累积因子。结果表明，SO 样品可能是一种安全的伽马辐射防护材料。获取玻璃陶瓷的去除截面以确定玻璃陶瓷阻止快中子的能力。重晶石和锆英石的加入提高了微晶玻璃的密度和防中子能力。最后，使用质量阻止本领和投射范围参数研究了玻璃陶瓷阻止带电α和质子粒子的能力。结论是带电粒子的射程在SO玻璃陶瓷中最短。本工作的推论将有助于确定重晶石和锆石对玻璃陶瓷核屏蔽能力的影响。使用质量阻止能力和投射范围参数研究了玻璃陶瓷阻止带电α和质子粒子的能力。结论是带电粒子的射程在SO玻璃陶瓷中最短。本工作的推论将有助于确定重晶石和锆石对玻璃陶瓷核屏蔽能力的影响。使用质量阻止能力和投射范围参数研究了玻璃陶瓷阻止带电α和质子粒子的能力。结论是带电粒子的射程在SO玻璃陶瓷中最短。本工作的推论将有助于确定重晶石和锆石对玻璃陶瓷核屏蔽能力的影响。