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波兰核医学医院室内空气中碘活度的测量作为内照射剂量评估的一种工具。

Measurement of I activity in air indoor Polish nuclear medical hospital as a tool for an internal dose assessment.

作者信息

Brudecki K, Szczodry A, Mróz T, Kowalska A, Mietelski J W

机构信息

Institute of Nuclear Physics, Polish Academy of Sciences, Radzikowskiego 152, 31-342, Krakow, Poland.

Department of Endocrinology and Nuclear Medicine Holycross Cancer Center, Artwińskiego 3, 25-734, Kielce, Poland.

出版信息

Radiat Environ Biophys. 2018 Mar;57(1):77-82. doi: 10.1007/s00411-017-0724-3. Epub 2017 Dec 14.

DOI:10.1007/s00411-017-0724-3
PMID:29243128
原文链接:https://pmc.ncbi.nlm.nih.gov/articles/PMC5816111/
Abstract

This paper presents results of I air activity measurements performed within nuclear medical hospitals as a tool for internal dose assessment. The study was conducted at a place of preparation and administration of I ("hot room") and at a nurse station. I activity measurements were performed for 5 and 4 consecutive working days, at the "hot room" and nurse station, respectively. Iodine from the air was collected by a mobile HVS-30 aerosol sampler combined with a gas sampler. Both the gaseous and aerosol fractions were measurement. The activities in the gaseous fraction ranged from (28 ± 1 Bq m) to (492 ± 4) Bq m. At both sampling sites, the activity of the gaseous iodine fraction trapped on activated charcoal was significantly higher than that of the aerosol fraction captured on Petrianov filter cloth. Based on these results, an attempt has been made to estimate annual inhalation effective doses, which were found to range from 0.47 mSv (nurse female) to 1.3 mSv (technician male). The highest annual inhalation equivalent doses have been found for thyroid as 32, 27, 13, and 11 mSv, respectively, for technician male, technical female, nurse male, and nurse female. The method presented here allows to fill the gaps in internal doses measurements. Moreover, because method has been successful used for many years in radioactive contamination monitoring of air in cases of serious nuclear accidents, it should also be used in nuclear medicine.

摘要

本文介绍了在核医学医院内进行的碘-131空气活度测量结果,以此作为内照射剂量评估的一种手段。该研究在碘-131的制备和给药场所(“热室”)以及护士站进行。分别在“热室”和护士站连续5个和4个工作日进行了碘-131活度测量。空气中的碘通过与气体采样器结合的移动式HVS-30气溶胶采样器收集。对气态和气溶胶部分都进行了测量。气态部分的活度范围为(28±1)Bq/m³至(492±4)Bq/m³。在两个采样点,捕获在活性炭上的气态碘部分的活度明显高于捕获在彼得罗夫滤布上的气溶胶部分的活度。基于这些结果,尝试估算了年吸入有效剂量,发现其范围为0.47mSv(护士女性)至1.3mSv(技术人员男性)。技术人员男性、技术人员女性、护士男性和护士女性的甲状腺年吸入当量剂量最高,分别为32、27、13和11mSv。这里介绍的方法可以填补内照射剂量测量方面的空白。此外,由于该方法多年来已成功用于严重核事故情况下空气的放射性污染监测,因此也应在核医学中使用。

https://cdn.ncbi.nlm.nih.gov/pmc/blobs/c1d3/5816111/271bf7c89f1a/411_2017_724_Fig1_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/c1d3/5816111/271bf7c89f1a/411_2017_724_Fig1_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/c1d3/5816111/271bf7c89f1a/411_2017_724_Fig1_HTML.jpg

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