Environmental dose values are critical for human health in non-destructive analysis systems. The International Commission on Radiological Protection (ICRP) has defined specific limitations for permissible dose values. This study assesses the dose distribution of a prototype analysis device utilizing Californium-252 (252Cf) radioactive material through both Monte Carlo simulations and laboratory experiments. Conducted at the Istanbul Technical University (ITU) Energy Institute, the experimental investigation measured gamma-ray and neutron dose values surrounding the device. The objective was to compare dose maps generated by the Monte Carlo-based GEANT4 code with experimental data. Ten dose maps were created, and fundamental statistical analyses were performed. Results indicate that the dose values on the operator’s working surface of the prototype device are within ICRP limits, not exceeding 1 millisievert (mSv) annually, with an effective dose rate of 0.949±0.052 mSv per year. These findings underscore the device’s potential for safe and effective use in radiation safety and environmental dose assessment.

中文翻译：

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使用 Monte Carlo 模拟和实验结果验证基于 252Cf 的无损在线元素分析设备的剂量映射


在无损分析系统中，环境剂量值对人类健康至关重要。国际辐射防护委员会 （ICRP） 定义了允许剂量值的具体限制。本研究通过蒙特卡洛模拟和实验室实验评估了使用 Californium-252 （252Cf） 放射性材料的原型分析设备的剂量分布。这项实验调查在伊斯坦布尔技术大学 （ITU） 能源研究所进行，测量了设备周围的伽马射线和中子剂量值。目的是将基于 Monte Carlo 的 GEANT4 代码生成的剂量图与实验数据进行比较。创建了 10 张剂量图，并进行了基本统计分析。结果表明，原型设备操作者工作表面的剂量值在 ICRP 限值范围内，每年不超过 1 毫西弗 （mSv），每年有效剂量率为 0.949±0.052 mSv。这些发现强调了该设备在辐射安全和环境剂量评估中安全有效使用的潜力。