Radiation dose to technicians per nuclear medicine procedure: comparison between technetium-99m, gallium-67, and iodine-131 radiotracers and fluorine-18 fluorodeoxyglucose
Radiation dose to technicians per nuclear medicine procedure: comparison between technetium-99m, gallium-67, and iodine-131 radiotracers and fluorine-18 fluorodeoxyglucose
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DOI:
10.1007/s002590050164
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发表时间:
1997-11-01
期刊:
影响因子:
--
通讯作者:
Bombardieri, E
中科院分区:
文献类型:
--
作者:
Chiesa, C;DeSanctis, V;Bombardieri, E
The aim of this study was to determine the non-extremity gamma dose received by a technician while performing an ordinary nuclear medicine procedure or a static (i.e. without blood sampling) fluorine-18 fluorodeoxyglucose (FDG) positron emission tomography (PET) study, The dose per patient was measured by means of a commercial electronic pocket Geiger Mueller dosimeter, worn in the upper left pocket of the overalls. This was previously tested by exposure to known point sources of technetium-99m, gallium-67, iodine-131 and fluorine-18 in the air. A further test was performed with Tc-99m, I-131 and F-18 sources inserted in a water phantom to simulate the condition of high scattering degradation of the primary radiation due to the patient's tissues, Subsequently, the dose was measured by two technicians for a total of 314 clinical cases, covering the most common nuclear medicine procedures, including 44 static, two-level FDG PET studies with repositioning of lire patient on the couch between the transmission and the emission scan and seven whole-body PET studies. The dose read by the dosimeter was corrected for environmental background and for detector efficiency measured with sources in the air. For a limited subset of cases, the time spent close to patients was also measured. Doses were then estimated by a crude non-absorbing point source approximation and by using experimental dose rates. A comparison between experimental. and estimated doses, as well as with previously published data, completed the work. For most of the conventional procedures, the measured dose per procedure proved to be within the range 0.2-0.4 mu Sv, except for equilibrium angiocardioscintigraphy (1.0 +/- 0.5 mu Sv) and Tc-99m-sestamibi single-photon emission tomography (1.7 +/- 1.0 mu Sv), Comparison with data published in the last 20 years shows that our values are generally lower. The current more favourable working conditions are a result of technological improvements (for instance two-head gamma cameras capable of whole-body studies), and safer shielding and distance from patients. Two-level PET gave 11.5 +/- 4.4 mu Sv and whole-body PET 5.9 +/- 1.2 mu Sv. In a subset of patients these values could be subdivided into the separate contributions from each phase of the procedure. They were: 0.11 +/- 0.04 mu Sv for daily quality assurance, 2.9 +/- 3.0 mu Sv for two transmission scans, 0.3 +/- 0.1 mu Sv for syringe preparation, 2.8 +/- 1.8 mu Sv for injection and escorting the patient to the waiting room, 1.7 +/- 1.5 mu Sv for a whole body emission scan, 7.7 +/- 5.2 mu Sv for two emission scans, and 0.8 +/- 0.2 mu Sv for patient departure. The higher value from PET by comparison with conventional procedures is attributable to the higher specific gamma constant of F-18, as well as the longer time required for accurate positioning.