Faculty of Safety Engineering and Civil Protection, The Main School of Fire Service, 52/54 Słowackiego Street, 01-629 Warsaw, Poland.
Central Laboratory for Radiological Protection, 7 Konwaliowa Street, 03-194 Warsaw, Poland.
Int J Environ Res Public Health. 2022 Sep 16;19(18):11695. doi: 10.3390/ijerph191811695.
It has been analyzed in this article the radioactivity concentrations of Ra, Th, K and radiological hazard parameters in different types of cements commonly used in Poland and available on the Polish market. The radiological hazard parameters are, in particular, absorbed gamma dose rate, annual effective dose, radium equivalent activity, the external hazard index, and the gamma and alpha indices. The radionuclide activities of the most important radionuclides Ra, Th, K have been determined by gamma-ray spectrometry with the use of two kinds of spectrometers of different operational parameters. One performed also measurements on 30-day and 45-day aged samples as to verify if there is a statistically significant difference in radioactivity concentration for shorter and longer aging time. The radioactivity concentrations in the cement samples ranged from 21.7-75.7 Bq·kg for Ra, 12.3-47.3 Bq·kg for Th to 123-430 Bq·kg for K. The radiological parameters in cement samples were calculated as follows: mean radium equivalent activity = 127 Bq·kg, mean absorbed gamma dose rate = 115 nGy·h, mean annual effective dose = 570 µSv·y, external hazard index = 0.32, internal hazard index = 0.51, mean activity concentration index = 0.47 and mean alpha index = 0.28. The results were compared with the reported data from other countries and the international standard values given by European Commission (EC) and United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR 2000). Finally, thorough statistical analysis has been performed.
本文分析了波兰市场上常见的不同类型水泥中的 Ra、Th、K 的放射性浓度以及各种辐射危险参数。这些辐射危险参数主要包括 γ 吸收剂量率、年有效剂量、镭当量活度、外照射指数以及 γ 和 α 指数。通过使用两种不同操作参数的光谱仪,对最重要的放射性核素 Ra、Th、K 的γ射线光谱进行了测定。其中一台光谱仪还对 30 天和 45 天龄期的样品进行了测量,以验证较短和较长老化时间的放射性浓度是否存在统计学上的显著差异。水泥样品中的放射性浓度范围为 Ra 为 21.7-75.7 Bq·kg,Th 为 12.3-47.3 Bq·kg,K 为 123-430 Bq·kg。对水泥样品中的辐射参数进行了计算,结果如下:镭当量活度平均值为 127 Bq·kg,γ 吸收剂量率平均值为 115 nGy·h,年有效剂量平均值为 570 µSv·y,外照射指数平均值为 0.32,内照射指数平均值为 0.51,活度浓度指数平均值为 0.47,α 指数平均值为 0.28。将这些结果与其他国家的报告数据以及欧洲委员会(EC)和联合国原子辐射效应科学委员会(UNSCEAR 2000)给出的国际标准值进行了比较。最后,还进行了彻底的统计分析。