Nuclear Technology Laboratory
Department of Electrical & Computer Engineering,
Aristotle University of Thessaloniki,
Macedonia, Greece.

Nuclear Technology Laboratory

Radiation Protection Dosimetry paper abstract

Citation: Radiat. Prot. Dosim. 74(1-2), pp 97-101 (1997)

Gamma Ray Spectrometry for the Determination of Absorbed Dose Rate in the Air Following Myocardial Perfusion Scintigraphy with 201Tl
A. Clouvas, S. Xanthos and M. Antonopoulos-Domis

The time dependence of the absorbed dose rate in air at a distance of 1 m from a patient who was undergoing myocardial perfusion scintigraphy with 201Tl was measured. The absorbed dose rate was deduced by in situ gamma ray spectrometry using a 'calibrated' portable Ge detector which allows the direct measurement of spectral dose rate distribution in the surroundings of a source without any assumption about the source geometry. The decrease of the absorbed dose rate with time can be expressed by a single exponential decay. The effective and biological half-lives of 201Tl were estimated to be 63 h and 20 days respectively. The total absorbed dose in air at a distance of 1 m from the patient was found to be 0.03 mGy which, converted to effective dose, gives 0.03 mSv which is small compared with the arithmetic annual mean worldwide, weighted for population, effective dose due to terrestrial gamma rays (0.46 mSv) and cosmic rays (0.38 mSv).
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