Abstract
The use of unsealed radiation sources in nuclear medicine can lead to important incorporation of radionuclides, especially for occupationally exposed individuals (OEIs) during production and handling of radiopharmaceuticals. In this study, computer simulation was proposed as an alternative methodology for evaluation of the absorbed dose distribution and for the effective dose value in OEIs. For this purpose, the Exposure Computational Model (ECM) which is named as FSUP (Female Adult Mesh - supine) were used. This ECM is composed of: voxel phantom FASH (Female Adult MeSH) in the supine position, the MC code EGSnrc and an algorythm simulator of general internal source. This algorithm was modified to adapt to specific needs of the positronic emission from FDG-18F. The obtained results are presented as absorbed dose/accumulated activity. To obtain the absorbed dose distribution it was necessary to use accumulative activity data from the in vivo bioassay. The absorbed dose distribution and the value of estimated effective dose in this study did not exceed the limits for occupational exposure. Therefore, the creation of a database with the distribution of accumulated activity is suggested in order to estimate the absorbed dose in radiosensitive organs and the effective dose for OEI in similar environment.
Highlights
The use of nuclear technology has grown considerably in numerous areas, increasing the production of radioactive sources and the number of occupationally exposed individuals (OEI) subjected to radionuclides
It is routinely produced at Divisão de Produção de Radiofármacos (DIPRA), Centro Regional de Ciências Nucleares do Nordeste (CRCNNE/Comissão Nacional de Energia Nuclear (CNEN)), where the methodology for internal monitoring of OEIs was implemented through in vivo bioassay technique [2]
This paper shows an alternative methodology used to obtain the dosimetric evaluation by experimental measurements from in vivo internal monitoring of OEIs data and computational simulations using an Exposure Computational Model (ECM) is presented
Summary
The use of nuclear technology has grown considerably in numerous areas, increasing the production of radioactive sources and the number of occupationally exposed individuals (OEI) subjected to radionuclides. Its accurate estimation is essential for radioprotection of the OEIs. In nuclear medicine, the use of open radiation sources can lead to significant incorporation of radionuclides, especially during the production and handling of radiopharmaceuticals procedures [1]. The radiopharmaceutical FDG-18F is the positron emitter most currently used in PET scans (Positron Emission Tomography). It is routinely produced at Divisão de Produção de Radiofármacos (DIPRA), Centro Regional de Ciências Nucleares do Nordeste (CRCNNE/CNEN), where the methodology for internal monitoring of OEIs was implemented through in vivo bioassay technique [2]. The incorporated activity data resulting from this technique was used to obtain the distribution of absorbed dose
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