电离辐射测量系统在核事故期间实时有效剂量优化寻路解决方案中的适用性

Fire Pub Date : 2024-04-16 DOI:10.3390/fire7040142
Attila Zsitnyányi, János Petrányi, Jácint Jónás, Zoltán Garai, L. Kátai-Urbán, Iván Zádori, István Kobolka
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引用次数: 0

摘要

减少通过核事故污染区撤离的伤员的有效剂量是应急服务的基本要求。在这种情况下,有必要为消防救援车辆开发一种剂量优化的路线寻找方法,其中包括开发一个实时决策支持测量和评估系统。该系统可确定并显示测试区域内可能路线的辐射照射情况。车内和车外的系统可测量环境剂量当量率、伽马能谱以及空气中的放射性气溶胶和碘含量。该方法使用安装在车辆外部的伽马辐射测量 NaI(Tl)闪烁探测器,利用先前记录的衰减对话函数来确定车内的剂量率,同时通过过滤器连续收集空气,并使用α、β和伽马辐射测量NaI(Tl)+PVT+ZnS(Ag)闪烁器来确定空气中的放射性活度浓度,利用这些测量值来确定所有路线和各种车辆的有效剂量。车辆的能量屏蔽效应、集体防护设备的过滤效率以及车辆的速度和行驶时间都被考虑在内。测量结果通过使用不同活度和能量水平的伽马点源进行了验证。真实条件下的测量结果和模拟中使用的三种不同车辆和行人的真实事故数据证明了该系统的适用性。根据我们的模型计算,在核事故中,吸入放射性气溶胶所造成的剂量几乎比尘埃污染造成的外部伽马辐射高出一个数量级。选择合适的运输工具及其路线取决于事故现场可以测量到的频谱,尤其是该地区空气中可以测量到的放射性气溶胶浓度。在使用辐射测量探测器时,必须考虑运载工具的屏蔽效果,特别是在使用重型屏蔽运载工具时。该方法为在救援行动中减少事故受害者和急救人员的健康损害提供了极好的机会。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Applicability of an Ionising Radiation Measuring System for Real-Time Effective-Dose-Optimised Route Finding Solution during Nuclear Accidents
The reduction in the effective dose of evacuated injured persons through contaminated areas of nuclear accidents is an essential emergency services requirement. In this context, there appeared a need to develop a dose-optimised route finding method for firefighting rescue vehicles, which includes the development of a real-time decision support measurement and evaluation system. This determines and visualises the radiation exposure of possible routes in a tested area. The system inside and outside of the vehicle measures the ambient dose equivalent rate, the gamma spectra, and also the airborne radioactive aerosol and iodine levels. The method uses gamma radiation measuring NaI(Tl) scintillation detectors mounted on the outside of the vehicle, to determine the dose rate inside the vehicle using the previously recorded attenuation conversation function, while continuously collecting the air through a filter and using an alpha, beta, and gamma radiation measuring NaI(Tl)+ PVT + ZnS(Ag) scintillator to determine the activity concentration in the air, using these measured values to determine the effective dose for all routes and all kinds of vehicles. The energy-dependent shielding effect of the vehicle, the filtering efficiency of the collective protection equipment, and the vehicle’s speed and travel time were taken into account. The results were validated by using gamma point sources with different activity and energy levels. The measurement results under real conditions and available real accident data used in our simulations for three different vehicles and pedestrians proved the applicability of the system. During a nuclear accident based on our model calculations, the inhalation of radioactive aerosols causes a dose almost an order of magnitude higher than the external gamma radiation caused by the fallout contamination. The selection of the appropriate vehicle and its route is determined by the spectrum that can be measured at the accident site but especially by the radioactive aerosol concentration in the air that can be measured in the area. In the case of radiation measuring detectors, the shielding effect of the carrier vehicle must be taken into account, especially in the case of heavy shielding vehicles. The method provides an excellent opportunity to reduce the damage to the health of accident victims and first responders during rescue operations.
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