Huang Lihua,Zheng Qishan,Zhang Yan,Zheng Senxin,Wei Weiqi.Preliminary study on assessment of internal dose to workers exposed to 131I radionuclide[J].Chinese Journal of Radiological Medicine and Protection,2021,41(12):898-905
Preliminary study on assessment of internal dose to workers exposed to 131I radionuclide
Received:May 24, 2021  
DOI:10.3760/cma.j.issn.0254-5098.2021.12.004
KeyWords:Internal exposure  Dose assessment  Nuclear medicine  131I  Radiopharmaceutical production
FundProject:福建省自然科学基金(2019J01094)
Author NameAffiliationE-mail
Huang Lihua Fujian Center of Prevention and Control of Occupational Diseases and Chemical Poisoning, Fuzhou, 350025, China  
Zheng Qishan Fujian Center of Prevention and Control of Occupational Diseases and Chemical Poisoning, Fuzhou, 350025, China  
Zhang Yan Fujian Center of Prevention and Control of Occupational Diseases and Chemical Poisoning, Fuzhou, 350025, China  
Zheng Senxin Fujian Center of Prevention and Control of Occupational Diseases and Chemical Poisoning, Fuzhou, 350025, China  
Wei Weiqi Fujian Center of Prevention and Control of Occupational Diseases and Chemical Poisoning, Fuzhou, 350025, China fjwq2002@163.com 
Hits: 2626
Download times: 871
Abstract::
      Objective To explore the assessment methodology for internal dose to workers exposed to 131I radionuclide. Methods Workers were chosen in a 131I radiopharmaceutial manufacturer and a nuclear medicine department in a hospital using 131I to treat hyperthyroidism and thyroid cancer. A portable high purity germanium (HPGe) gamma spectrometer was used to measure the content of 131I in the thyroid for 4 consecutive times in a period of 7 d. The internal dose was estimated combining with the work rotation mode for workers dealing with 131I. Results When the monitoring month was used as a typical month to estimate the internal dose, the annual committed effective dose was 0.09-1.93 mSv for the production staff engaged in the repackaging of 131I radiopharmaceuticals in the surveyed enterprise, and 0.06-0.58 mSv for the nuclear medicine staff in the surveyed hospital. After adjusting the monitoring result of the current monitoring period based on the rotation mode, the annual committed effective dose was estimated to be 0.06-1.22 mSv for radiopharmaceutical production workers and 0.03-0.15 mSv for nuclear medicine workers, respectively. Conclusions In the assessment of internal dose to radiation workers exposed to 131I, using a single time measurement result to estimate the annual dose would lead to a larger error. In the case of continuous monitoring, the result of subsequent monitoring periods should be corrected according to the result of previous monitoring periods. In order to accurately estimate the internal dose of workers exposed to 131I, it is necessary to take full account of the 131I exposure pattern, time and frequency and the internal contamination route. For workers who may be exposed to 131I with potential internal dose greater than 1 mSv/year, a 14 day-routine monitoring period was appropriate.
HTML  View Full Text  View/Add Comment  Download reader
Close

Copyright©    Editorial Office of Chinese Journal of Radiological Medicine and Protection    

Beijing ICP No. 05020547 -2

Address: 2 Xinkang Street, Dewai, Beijing 100088, China

Telephone:010-62389620; Email:cjrmp@cjrmp.sina.net

Technical Support:Beijing E-tiller CO.,LTD.

Visitors:9075345  On-line:0

v
Scan QR Code
&et=05856B6FACD30C99AAF724D5AA8F81504F0E560BA63E984B49E234E37C2A8717E3C22220CC099A56CFD6DF22831A516B07333A5EF08C3EB831B418BD5B9A9B84EBB1B7ABAE9B9F7BA2E4D88488134E638BB663680BB43200BF6E3825E88F0BD97ACEE7EE8ADDD25F&pcid=A9DB1C13C87CE289EA38239A9433C9DC&cid=D4D466D60FDC1A5A&jid=5E4353813E091AB841B02B880782B82C&yid=9475FABC7A03F4AB&aid=AA4FE43705B0D4A77F8EB2FA8402DAC3&vid=&iid=59906B3B2830C2C5&sid=9124D83E61CF1CD0&eid=FE2777263ADBA5FE&fileno=20211204&flag=1&is_more=0"> var my_pcid="A9DB1C13C87CE289EA38239A9433C9DC"; var my_cid="D4D466D60FDC1A5A"; var my_jid="5E4353813E091AB841B02B880782B82C"; var my_yid="9475FABC7A03F4AB"; var my_aid="AA4FE43705B0D4A77F8EB2FA8402DAC3";