基于公众剂量估算的水环境总β活性排放限值修订:一项操作性研究

Hukum Singh, Teena Goel, V. Kadwad, P. Mukherjee
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摘要

德里辐射和同位素技术区域中心(BRIT)产生的低水平液体废水,一般在经过符合孟买原子能管理委员会授权的法规要求的适当处理(对短寿命放射性核素进行延迟、衰变和稀释)后排放到水生环境中。英国-德里区域中心在生产可用于人类注射的99mTc-放射性药物时,产生含有短寿命放射性核素99Mo (T1/2−66.7小时)和99mTc (T1/2−6.02小时)的液体流出物,以及长寿命放射性核素99Tc (T1/2−2.13 × 105年)。这种在清洗受放射性污染的玻璃器皿过程中产生的废液本质上是无机的,储存在02个污水池中(每个容量50立方米),以延缓和衰变短寿命放射性核素。该中心还计划在未来生产和供应68Ga放射性药物。其中一些放射性核素可能通过各种自然途径到达饮用水。放射性核素在饮用水中的含量超过一定水平,可能通过摄入途径对公众造成辐射剂量。遵守监管机构规定的废水放射性核素浓度、总活度限值和其他基本安全要求,有助于将公众辐射剂量降至最低。本文试图根据世界卫生组织规定的饮用水标准限值,推导出英国德里区域中心总β活性对内陆场地水环境的年排放限值。本文还讨论了英国德里区域中心实际排放放射性液体废水所受到的有效剂量。
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Revision of discharge limit of gross beta activity to the aquatic environment based on public dose estimation: An operational study
Low-level liquid effluents generated from Regional Centre, Board of Radiation, and Isotope Technology (BRIT), Delhi, are generally discharged to the aquatic environment after suitable treatment (delay, decay, and dilution for short-lived radionuclides) conforming the regulatory compliance as authorized by Atomic Energy Regulatory Board, Mumbai. The Regional Center, BRIT-Delhi is generating the liquid effluents containing short-lived radionuclides 99Mo (T1/2−66.7 h) and 99mTc (T1/2−6.02 h) and also long-lived radionuclide 99Tc (T1/2−2.13 × 105 years) from the production of ready to use 99mTc-radiopharmaceuticals as human injectable product. This liquid waste generated during the washing of radioactive contaminated glassware is inorganic in nature and is stored in 02 number of sump tanks (capacity 50 m3 each) for delay and decay of short-lived radionuclides. The center has also planned to produce and supply 68Ga radiopharmaceuticals in future. There is a possibility that some of these radionuclides may reach the drinking water by various natural pathways. The presence of radionuclides in the drinking water above certain level may result in radiation dose to the public through the ingestion pathways. The observance of prescribed radionuclide concentration in waste water, total activity limits, and other basic safety requirements stipulated by the regulatory body help to minimize the public radiation dose. This article is an effort to derive the annual discharge limit for gross β activity at Regional Center, BRIT-Delhi to the aquatic environment of an inland site based on the drinking water standard limits prescribed by the World Health Organization. This article also discusses the effective dose received by the actual discharge of radioactive liquid effluent from the Regional Center, BRIT-Delhi.
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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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