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    A Computer Program for Calculation of Approximate Embryo/Fetus Radiation Dose in Nuclear Medicine Applications
    (Galenos Publ House, 2012) Bayram, Tuncay; Sonmez, Bircan
    Objective: In this study, we aimed to make a computer program that calculates approximate radiation dose received by embryo/fetus in nuclear medicine applications. Material and Methods: Radiation dose values per MBq-1 received by embryo/fetus in nuclear medicine applications were gathered from literature for various stages of pregnancy. These values were embedded in the computer code, which was written in Fortran 90 program language. Results: The computer program called nmfdose covers almost all radiopharmaceuticals used in nuclear medicine applications. Approximate radiation dose received by embryo/fetus can be calculated easily at a few steps using this computer program. Conclusion: Although there are some constraints on using the program for some special cases, nmfdose is useful and it provides practical solution for calculation of approximate dose to embryo/fetus in nuclear medicine applications.
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    Öğe
    Radiation Dose to Technologists per Nuclear Medicine Examination and Estimation of Annual Dose
    (Soc Nuclear Medicine Inc, 2011) Bayram, Tuncay; Yilmaz, A. Hakan; Demir, Mustafa; Sonmez, Bircan
    Conventional diagnostic nuclear medicine applications have been continuously increasing in most nuclear medicine departments in Turkey, but to our knowledge no one has studied the doses to technologists who perform nuclear medicine procedures. Most nuclear medicine laboratories do not have separate control rooms for technologists, who are quite close to the patient during data acquisition. Technologists must therefore stay behind lead shields while performing their task if they are to reduce the radiation dose received. The aim of this study was to determine external radiation doses to technologists during nuclear medicine procedures with and without a lead shield. Another aim was to investigate the occupational annual external radiation doses to Turkish technologists. Methods: This study used a Geiger-Mu ller detector to measure dose rates to technologists at various distances from patients (0.25, 0.50, 1, and 2 m and behind a lead shield) and determined the average time spent by technologists at these distances. Deep-dose equivalents to technologists were obtained. The following conventional nuclear medicine procedures were considered: thyroid scintigraphy performed using Tc-99m pertechnetate, whole-body bone scanning performed using Tc-99m-methylene diphosphonate, myocardial perfusion scanning performed using Tc-99m-methoxyisobutyl isonitrile, and Tl-201 (thallous chloride) and renal scanning performed using Tc-99m-dimercaptosuccinic acid. Results: The measured deep-dose equivalent to technologists per procedure was within the range of 0.13 +/- 0.05 to 0.43 +/- 0.17 mu Sv using a lead shield and 0.21 +/- 0.07 to 1.01 +/- 0.46 mu Sv without a lead shield. Also, the annual individual dose to a technologist performing only a particular scintigraphic procedure throughout a year was estimated. Conclusion: For a total of 95 clinical cases (71 patients), effective external radiation doses to technologists were found to be within the permissible levels. This study showed that a 2-mm lead shield markedly reduced the external dose to technologists. The doses to technologists varied significantly for different diagnostic applications. Consequently, the estimated annual dose to a technologist performing only a particular scintigraphic procedure is very different from one type of procedure to another. The results of this study should help in determining the rotation time of technologists in different procedures and differences in their individual techniques.