基于塑料闪烁体薄膜流动池的低活度浓度氚水原位探测器理论设计

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Xiaoyu Li , Zhi Chen
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引用次数: 0

摘要

为确保辐射安全,控制氚的潜在风险,低放射性浓度氚水的原位测量技术具有广泛的现实需求。为实现这一目标,我们利用塑料闪烁体薄膜(PSTF)和硅光电倍增管阵列(SiPM)从理论上设计了一种新型探测器。利用蒙特卡洛模拟分析了样品室厚度、塑料闪烁体厚度和样品室数量等关键参数,全面评估了影响能量沉积、光传输、探测效率和最小可探测放射性浓度(MDAC)的因素。结果表明,该系统的检测效率为 22.5%,在一分钟的计数时间内,三价水的 MDAC 为 6.909 Bq/mL。这种结构紧凑、灵敏度高的探测器非常适合环境监测和辐射安全领域的一系列应用。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
In-situ detector theoretical design for low-activity concentration tritiated water based on plastic scintillator thin film flow cell
In order to ensure radiation safety and control the potential risk of tritium, the in-situ measurement technology of low radioactive concentration tritiated water has wide practical demands.A novel detector was theoretically designed utilizing plastic scintillator thin films (PSTFs) and silicon photomultiplier arrays (SiPMs) to achieve this objective. Key parameters such as sample chamber thickness, plastic scintillator thickness, and the number of sample chambers were analyzed using Monte Carlo simulations, thoroughly evaluating factors influencing energy deposition, optical transmission, detection efficiency, and minimum detectable activity concentration (MDAC). The results demonstrated that the system achieved a detection efficiency of 22.5% with the MDAC of 6.909 Bq/mL for tritiated water over a counting time of one minute. This compact and highly sensitive detector configuration is well-suited for a range of applications in environmental monitoring and radiation safety.
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来源期刊
Fusion Engineering and Design
Fusion Engineering and Design 工程技术-核科学技术
CiteScore
3.50
自引率
23.50%
发文量
275
审稿时长
3.8 months
期刊介绍: The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.
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