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      Study on the radiation device of 241Am-Be neutron source and its dosimetric properties

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          Abstract

          Objective To design and build a set of experimental equipment for neutron radiation irradiation by using the 241Am-Be neutron source.

          Methods In the preliminary work, the spatial distribution data of the neutron energy spectrum and the gamma energy spectrum inside and outside the device were simulated by Monte Carlo method, and the changes of radiation fluence rate with spatial distribution was studied. The model of the 241Am-Be neutron device was established, and the neutron transport process in the irradiation field was studied using the method of shadow cone, inverse square law and other data analysis methods.

          Results Based on the simulation results, the normalized effective does of fast neutron fluence at the measurement point is about 72.9 pSv/n, and the one of photon fluence is about 3.04 pSv/γ. The ratio of effective dose of photon fluence to neuteon is about 4.17%.

          Conclusion Using Monte Carlo method, a standard model of 241Am-Be neutron source was constructed, the shadow cone design was optimized, and the feasibility of using the shadow cone conversion method to establish a standard neutron source radiation device was discussed.

          Abstract

          摘要: 目的 拟利用 241Am-Be 中子源设计并建立一套中子辐射照射实验装置。 方法 采用蒙特卡洛 (Monte Carlo) 方 法, 模拟计算装置内外中子能谱和 γ 能谱空间分布数据, 研宄中子注量等随空间分布的变化规律;初步建立镅铍中子 装置的数学模型, 采用影锥法、平方反比律验证等数据分析方法, 对中子输运过程进行研宄。 结果 模拟获得测量点 处归一化快中子注量有效剂量约为 72.9 pSv/n, 光子约为 3.04 pSv/γ, 光子注量有效剂量与中子注量有效剂量的比值约 为 4.17%。 结论 利用蒙特卡洛方法, 构建了镅铍中子源标准装置模型, 优化了影锥设计, 初步讨论了将影锥转换法用 于建立中子源辐射照射装置的可行性。

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          Author and article information

          Journal
          CJRH
          Chinese Journal of Radiological Health
          Chinese Preventive Medical Association (Ji’an, China )
          1004-714X
          01 April 2021
          01 August 2021
          : 30
          : 2
          : 168-172
          Affiliations
          [1] 1Editorial Department of 《Atomic Energy Science and Technology》, China Institute of Atomic Energy, Beijing 102413 China
          [2] 2School of Nuclear Science and Technology, Lanzhou University, Lanzhou 730000 China
          [3] 3National Institute for Radiological Protection, Chinese Center for Disease Control and Prevention, Beijing 100088 China
          [4] 4The Beijing Prevention and Treatment Hospital of Occupational Disease for Chemical Industry, Beijing 100089 China
          Author notes
          Corresponding author: CAO Lei, E-mail: caolnirp@ 123456163.com
          Article
          j.issn.1004-714X.2021.02.010
          10.13491/j.issn.1004-714X.2021.02.010
          9097dcb7-11ef-4c53-8812-bc55dd6936ec
          © 2021 Chinese Journal of Radiological Health

          This is an open-access article distributed under the terms of the Creative Commons Attribution 4.0 Unported License (CC BY-NC 4.0), which permits unrestricted use, distribution, and reproduction in any medium, provided the original author and source are credited. See https://creativecommons.org/licenses/by-nc/4.0/.

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          Categories
          Journal Article

          Medicine,Image processing,Radiology & Imaging,Bioinformatics & Computational biology,Health & Social care,Public health
          Shadow Cone Method, 241Am-Be Neutron Source,Monte Carlo Calculation

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