非密封源工作场所的环评是否可以不用考虑个人剂量？
非密封源工作场所的环评是否可以不用预测个人剂量？如果可以，有什么依据？我现在在做一个放射性同位素应用的环评，是一个丙级非密封源工作场所，项目还没有建起来不能实测，另外也实在找不到类比数据，哪位是否可以帮个忙？
如果有类比数据麻烦发我邮箱：57046144@qq.com感激不尽！ 本帖最后由 0052020105li 于 2010-11-8 12:10 编辑
ttp://www.shendusou.com/search?q=%E9%9D%9E%E5%AF%86%E5%B0%81%E6%BA%90%E5%B7%A5%E4%BD%9C%E5%9C%BA%E6%89%80
http://www.shendusou.com/search?q=cview:hMa0LIoQIW&l=all
l 本帖最后由 0052020105li 于 2010-11-8 13:04 编辑
Extremity Dosimetry for Radiation Workers Handling Unsealed Radionuclides in Nuclear Medicine Departments in India
Tandon, Pankaj*; Venkatesh, Meera†; Bhatt, B C.‡
以下为摘要部分
In India, for the past five decades, whole body radiation dose of radiation workers has been monitored by means of film and thermoluminescent dosimeter (TLD) badges worn on the body. However, there are no provision/regulatory requirements to monitor doses received at the extremities, i.e., to fingers. Finger dose monitoring is essential for controlling the extremity dose limits for occupational personnel handling unsealed radioactive sources. In order to estimate the doses received in various types of procedures using unsealed sources, finger dose monitoring was carried out in 54 major institutions in the country using a specially designed plastic finger ring embedded with a TLD. The maximum finger dose of occupational workers involved in handling 99mTc in such activities as extraction and radiopharmacy work is 0.35 mSv GBq-1; during injection of radiopharmaceuticals and scintigraphy, the doses were observed to be 1 and 0.95 mSv GBq-1, respectively. Similarly, while handling 18F-FDG, the maximum doses received during dispensing, injection, and scintigraphy were 0.098, 0.324, and 0.56 mSv GBq-1, respectively. The maximum radiation dose received during 188Re/186Re balloon angioplasty and while handling 153Sm was 3.92 and 6.5 mSv GBq-1, respectively. All the doses recorded were well within the prescribed limit. However, monitoring of these doses periodically would help in compiling the feedback regarding the work practices followed in institutions handling radioisotopes in the country and would also help in maintaining a record of safe work procedures while handling radioisotopes. An assessment of annual whole-body occupational radiation exposure in Ireland (1996–2005)
Whole-body occupational exposure to artificial radiation sources in Ireland for the years 1996–2005 has been reviewed. Dose data have been extracted from the database of the Radiological Protection Institute of Ireland, which contains data on >95% of monitored workers. The data have been divided into three sectors: medical, industrial and education/research. Data on exposure to radon in underground mines and show caves for the years 2001–05 are also presented. There has been a continuous increase in the number of exposed workers from 5980 in 1996 to 9892 in 2005. Over the same time period, the number of exposed workers receiving measurable doses has decreased from 676 in 1996 to 189 in 2005 and the collective dose has also decreased from 227.1 to 110.3 man millisievert (man mSv). The collective dose to workers in the medical sector has consistently declined over the 10-y period of the study while that attributable to the industrial sector has remained reasonably static. In the education/research sector, the collective dose typically represents 5% or less of the total collective dose from all practices. Over the 10 y of the study, a total of 77 914 annual dose records have been accumulated, but only 4040 (<6%) of these represent measurable radiation doses in any given year. Over the same time period, there were 283 instances in which exposed workers received individual annual doses >1 mSv and 21 of these exceeded 5 mSv. Most of the doses >1 mSv were received by individuals working in diagnostic radiology (which also includes interventional radiology) in hospitals and site industrial radiography. There has been only one instance of a dose above the annual dose limit of 20 mSv. Evaluating the data for the period 2001–05 separately, the average annual collective dose from the medical, industrial and educational/research sectors are ～60, 70 and 2 man mSv with the average dose per exposed worker who received a measurable dose being 0.32, 0.79 and 0.24 mSv, respectively. Diagnostic radiology and site industrial radiography each represents >60% of the collective dose in their respective sectors. Available data on radon exposure in one underground mine and in three show caves indicate an annual collective dose of 75 man mSv from these work activities. By comparison, previous estimates of exposure of Irish air crew to cosmic radiation have given rise to an estimated collective dose of 12 000 man mSv. It can be concluded therefore that the natural radioactivity sources account for well >90% of all occupational exposure in Ireland. This evaluation does not include an estimate of exposure to radon in above-ground workplaces—these data are currently being evaluated and their inclusion will increase both the total occupational collective dose as well as the percentage of that dose due to natural radiation. 这篇文章还是相当不错的，值得一看 谢谢楼上各位的无私帮助！！ 本帖最后由 Lpp_219 于 2010-11-19 21:37 编辑
绕了一大圈,原来高手就在我身边.... 必须考虑个人剂量，这也是辐射环评最重要的目的之一。
所建议采取的一切措施，包括分区管理、使用有铅屏蔽的通风橱、带铅屏风的注射台、使用冷实验方法预习操作步骤等，都是为了尽可能降低工作人员和公众的个人受照剂量。
对于新建项目，完全可以通过理论计算估算人员个人剂量。 中文文献没英文摘要有参考价值。。。
求英文资料全文
页:
[1]
