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Lai, Y.C.; Huang, Y. F.; Chen, Y.W., E-mail: yuchla@hotmail.com
International Radiation Protection Association (IRPA), Fontenay-aux-Roses (France); Sociedad Argentina de Radioproteccion (SAR), Buenos Aires (Argentina); International Atomic Energy Agency (IAEA), Vienna (Austria); Pan American Health Organization (PAHO), Washington, DC (United States); World Health Organization (WHO), Geneva (Switzerland)2008
International Radiation Protection Association (IRPA), Fontenay-aux-Roses (France); Sociedad Argentina de Radioproteccion (SAR), Buenos Aires (Argentina); International Atomic Energy Agency (IAEA), Vienna (Austria); Pan American Health Organization (PAHO), Washington, DC (United States); World Health Organization (WHO), Geneva (Switzerland)2008
AbstractAbstract
[en] Full text: Short-term environment dose-rate assessments using real-time digital dosimeters within a Nuclear Medicine Department (NMD) are gaining more world-wide uses recently. In the past, conventional ion chamber-type survey-meters are used dominantly in environmental dose rates evaluation. Although it has suffered less gamma energy-dependency, but it is less sensitive in comparison with other digital dosimeters and more bulky in design that can hardly make it into a pocket size application. With modern electronic advancement and its shrinking in physical size, real-time personal dosimeter nowadays has gaining more popular to use a miniature G-M counter or a solid-state diode sensor, or even a NaI(Tl) scintillation device for ambient radiation monitoring. Radiation sensor operated in pulse-mode can never been used in doses or dose rates determination since each digital pulse has carried no energy information of the impinging gamma ray being interactive with, especially in the G-M counter or the diode sensor case. The raw count rates measured from a pulse-mode device are heavily dependent on the packaging of the sensor to make it less energy-sensitive. The doses or dose rates are then calculated by using a built-in conversion factor, based on a Cs-137 beam source calibration data conducted by various manufacturing vendors, to convert its raw counts into a so-called dose or dose-rate unit. In this study, we have focused our interests in the low energy response of the digital dosimeters from several brands currently for our in-house uses. Mainly, Tc-99m and I-131 in point sources and water phantoms detection configurations have been deployed to simulate our NMD outpatients for environment radiation monitoring purpose. The energy-dependent correction factors of the digital dosimeters will be evaluated by using calibrated Tc-99m or I-131 standard sources directly that has much lower gamma energy than the Cs-137 beam source of 661 keV. In the near future, we would extend this study to include the I-125 sources, with gamma energy of 35 keV, that have also been used routinely in our hospital. As a preliminary result of this on-going research project, we have found that the NaI(Tl) hand-held dosimeter has grossly over-estimated in the low energy dose response. The G-M counters are more energy-dependant in point source or beam source calibration. For environment radiation monitoring concern within our NMD, we found the energy-compensated G-M counter suffered the least in energy-dependency during water phantom calibration testing. (author)
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2008; 1 p; SAR; Buenos Aires (Argentina); IRPA 12: 12. International congress of the International Radiation Protection Association (IRPA): Strengthening radiation protection worldwide; Buenos Aires (Argentina); 19-24 Oct 2008; Abstract only
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Miscellaneous
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Conference
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BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, DAYS LIVING RADIOISOTOPES, DOSES, ELECTRON CAPTURE RADIOISOTOPES, HOURS LIVING RADIOISOTOPES, INTERMEDIATE MASS NUCLEI, INTERNAL CONVERSION RADIOISOTOPES, IODINE ISOTOPES, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, MEASURING INSTRUMENTS, MEDICINE, MONITORING, NUCLEI, ODD-EVEN NUCLEI, RADIOISOTOPES, TECHNETIUM ISOTOPES, YEARS LIVING RADIOISOTOPES
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