Development of techniques based on Monte Carlo simulations for clearance of Co-57 and Ge-68/Ga-68 sealed radioactive sources

Published: Apr 1, 2019
Sealed sources Clearance NaI(Tl) Gamma-ray spectrometry MCNPX simulations
Tatiana Siarafera
Eleni Ntalla
Dimitris Mavrikis
Angelos Markopoulos
Alexandra Ioannidou
Anastasia Savvidou
Sealed radioactive sources of Co-57 and Ge-68/Ga-68 are used for the calibration of various nuclear medicine systems like Gamma camera and PET imaging. After their useful life, these sealed sources need to be kept in control for decay until meeting the general clearance criterion. The aim of this work is to determine the activity of spent sealed radioactive sources of Ge-68 / Ga-68 and Co-57. For this purpose, techniques based on Monte Carlo simulation by the use of the MCNPX code was developed for evaluation of the 3”x3” NaI(Tl) scintillator efficiency for specific source–detector geometries. These techniques proved to be accurate. 
Article Details
  • Section
  • Poster contributions
Canberra Industries, Inc. GenieTM 2000 Gamma Analysis Spectroscopy Software
Richard B. Firestone, “Table of Isotopes”, Eighth Edition, Wiley Interscience, March, 1996
Kalfas et al., Nucl. Instrum. Methods Phys. Res. Sect. A 830 (2016) 265-274
Done et al., Appl. Rad. Isot. 114 (2016) 28-32
Joint Ministerial Order 1014 (FOR) 94, Official Gazette No. 216/B/06-03-2001, “Radiation Protection Regulations”. (in Greek)
Strahlenschutzverordnung (StSV), vom. 26 April 2017, Anhang 2 (Art. 2 Abs. 1 Bst. j, l und m sowie 194 Abs. 3)