南印度Kalpakkam多设施核电站伽马辐射监测的长期趋势

Deepu Radhakrishnan, M. Boopathy, V. Gopalakrishnan, P. Rakesh, S. Chandrasekaran, C. Srinivas, R. Venkatesan, B. Venkatraman
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引用次数: 2

摘要

在这项工作中,对Kalpakkam原子能部场址内收集的长期环境辐射监测数据进行了分析,这些数据来自2013年至2018年期间使用gamma racers (gt)等伽马监测仪和2016年至2018年期间位于场址边界1.25至2.5公里处的自主伽马剂量记录仪(AGDLs),分析了不同地点/风区/季节的剂量变化。平均背景剂量率在140-220 nGy/h范围内,除了在GT2位置发现的剂量率为400±20 nGy/h。据观察,探测器通常测量的是正常的本底剂量,有时由于马德拉斯核电站在正常运行期间暴露于41Ar烟柱而测量的剂量略高(高于本底)。监测器被分为四组:第一组到第四组。在冬季和东北季风季节,第1组探测器的剂量率高于正常水平;在夏季和西南季风季节,第3组和第4组探测器的剂量率高于正常水平;在第2组探测器的1至3月期间,剂量率高于正常水平。41Ar羽流过境期间的伽马剂量率在600-900 nGy/h范围内变化。分析了2016 - 2018年不同扇区因正常操作释放而产生的场区边界累积年有效剂量在11 ~ 114 μSv之间,明显低于公众年剂量限值(1000 μSv)。
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Long-term trends in gamma radiation monitoring at the multi-facility nuclear site, Kalpakkam, South-India
In this work, the analysis of the long-term environmental radiation monitoring data collected within the Department of Atomic Energy site, Kalpakkam using gamma monitors such as GammaTRACERS (GTs) from 2013 to 2018 and Autonomous Gamma Dose Loggers (AGDLs) located in the site boundary at distances from 1.25 to 2.5 km from 2016 to 2018 are presented with respect to dose variation in different locations/wind sectors/seasons. The average background dose rates are in the range of 140–220 nGy/h except at a location (GT2) where a dose rate of 400 ± 20 nGy/h is found. It is observed that the detectors generally measure the normal background doses and at times slightly higher doses (above background) due to exposure to 41Ar plume during normal operations from Madras Atomic Power Stations. The monitors were categorized into four groups: Group 1 to Group 4. Dose rates higher than normal were observed in Group 1 detectors during winter and North-east monsoon seasons and in Group 3 and Group 4 detectors during summer and South-west monsoon seasons and during January to March months in Group 2 detectors. The gamma dose rates during 41Ar plume transit vary in the range of 600–900 nGy/h. The cumulative annual effective doses at the site boundary, analyzed from 2016 to 2018, due to normal operational releases varied from 11 μSv to 114 μSv in different sectors which is significantly lower compared to annual dose limit (1000 μSv) for public.
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Theme 8. Emergency preparedness and response Theme 2. Radiation Safety and Protection in Nuclear Facilities Theme 1. Foundation Topics on Radiation Protection Philosophy and Risk Estimates Theme 7. Existing Exposures Theme 5. Nuclear instrumentation and system development
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