An investigation of neutron shielding and activation performances of four types of concrete for carbon ion therapy facility

电磁屏蔽 核工程 衰减 中子 离子 材料科学 碳纤维 放射化学 环境科学 蒙特卡罗方法 辐射防护 核物理学 物理 工程类 化学 复合材料 光学 复合数 数学 统计 有机化学
作者
Yao Yang,Fuhong Ma,Xirui Zhou,Wuyuan Li,Youwu Su,Chong Xu,Bocheng Jiang
出处
期刊:Applied Radiation and Isotopes [Elsevier BV]
卷期号:206: 111233-111233 被引量:8
标识
DOI:10.1016/j.apradiso.2024.111233
摘要

Carbon ions have unique physical and biological properties that allow for precise targeting of tumors while minimizing damage to surrounding healthy tissues. The emitted neutrons dominate the radiation field in the treatment room and pose challenges for radiological shielding. Concrete is extensively utilized in the construction of radiotherapy facilities due to its good shielding characteristics, and it can be easily poured into the desired shapes and thickness. The difference in composition of concrete affects the characteristics of neutron attenuation and activation performance. Therefore, the purpose of this study is to clarify the shielding properties and activation performances of four types of concrete for carbon ion therapy facilities. The Monte Carlo method is used to analyze the neutron spectra from thick targets upon carbon ion bombardment. Furthermore, the deep attenuation efficiency of the secondary neutron in different compositions of concrete is discussed. The shielding design is developed to ensure compliance with the prescribed dose limit outside the shielding during operation. Finally, the induced radioactivity in concrete is estimated for both short-term and long-term operation. The produced radionuclides inventories and depth profiling are determined. This study reveals the shielding and radioactivity issue of carbon ion therapy facilities and is expected to aid in the design or construction of similar facilities.
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