External radiation doses from patients administered with radiopharmaceuticals measurements and Monte Carlo simulation

Author:

Kinsara Abdul1,Abdul-Majid Samir1,El-Gammal Wael2,Albaghdadi Tarik3,Maimani Abdulraof3,Abulfaraj Waleed1

Affiliation:

1. King Abdulaziz University, Faculty of Engineering, Jeddah, Saudi Arabia

2. Permanent Radiation Safety Committee, Jeddah, Saudi Arabia

3. King Abdulaziz University, Faculty of Medicine, Jeddah, Saudi Arabia

Abstract

Monte Carlo simulations and dose measurements were performed for radionuclides in the whole body and trunks of different sizes in order to estimate external radiation whole body doses from patients administered with radiopharmaceuticals. Calculations were performed on cylindrical water phantoms whose height was 176 cm and for three body diameters: of 24 cm, 30 cm, and 36 cm. The investigated radionuclides were: 99mTc, 131I, 23I, 67Ga, 201Tl, and 111In. Measured and MCNP-calculated values were 2-6 times lower than the values calculated by the point source method. Additionaly, the total dose received by the public until a radionuclide is completely disintegrated was calculated. The other purpose of this work is to provide data on whole body and finger occupational doses received by technologists working in nuclear medicine. Data showed a wide variation in doses that depended on the individual technologist and the position of the dosimeter.

Publisher

National Library of Serbia

Subject

Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

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