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Assessment of the staff absorbed dose related to cyclotron operation and service in the production of 18F radiopharmaceuticals

Treść / Zawartość
Identyfikatory
Warianty tytułu
Języki publikacji
EN
Abstrakty
EN
Cyclotron accelerators are used to produce medical radioisotopes. One of the most important problems which may be encountered is malfunction of a part of the target or beam line which requires stopping of the bombardment and making a repair. The decision about doing the repair depends on the whole body dose rate in a target room. In this work, dosimetric conditions related to the production of 18FDG radiopharmaceutical were simulated by the Monte Carlo (MC) method. Independently, the dose rates were measured by 7 ICRU spherical body phantoms placed inside the liquid target room and the maze of the cyclotron. The radiation dose rate inside the target room depends on the duration of the bombardment and the time passed after stopping the bombardment. The correlation between duration of the bombardment and required time after stopping the bombardment to reach the absorbed dose rate less than 25 mi Sv/h, was calculated for the presence and absence of the irradiated target. The results showed that the repair can be started immediately after stopping of the proton bombardment only if the target has been ejected from the target room and the duration of bombardment has not taken more than 10 min.
Czasopismo
Rocznik
Strony
407--410
Opis fizyczny
Bibliogr. 11 poz., rys.
Twórcy
autor
autor
  • Department of Nuclear Engineering, Faculty of Advanced Sciences and Technologies, University of Isfahan, Isfahan, Iran Tel.: +98 311 793 4059, Fax: +98 311 793 2771
Bibliografia
  • 1. Al Rayyes AH (2010) Enriched water-H2 18O purification to be used in routine 18FDG production. Nukleonika 55:401–405
  • 2. Cember H, Johnson TE (2009) Introduction to Health Physics, 4th ed. McGraw-Hill Companies, New York
  • 3. Demir M, Demir B, Yasar D et al. (2010) Radiation doses to technologists working with 18F-FDG in a PET center with high patient capacity. Nukleonika 55:107–112
  • 4. IAEA (2000) Calibration of radiation protection monitoring instruments. Safety Reports Series no. 16. International Atomic Energy Agency, Vienna
  • 5. ICRP (1991) ICRP Publication 60: 1990 Recommendation of the ICRP. International Commission on Radiological Protection. Pergamon Press, New York
  • 6. ICRU (1993) Quantities and Units in Radiation Protection Dosimetry. ICRU Report 51. International Commission on Radiation Units and Measurements, Bethesda, MD
  • 7. Koning AJ, Rochman D (2009) TALYS-based evaluated nuclear data library. Nuclear Research and Consultancy Group
  • 8. Kuo MJ, Hsu FY, Hsu CH et al. (2010) Dose estimation of the radiation workers in the SK cyclotron center using dual-TLD method. Radiat Meas 45:691–693
  • 9. Moyers MF, Leyna DA (2009) Exposure from residual radiation after synchrotron shutdown. Radiat Meas 44:176–181
  • 10. Sadeghi M, Kakavand T, Rajabifar S, Mokhtari L, RahimiNezhad A (2009) Cyclotron production of 68Ga via proton-induced reaction on 68Zn target. Nukleonika 54:25–28
  • 11.Takacs S, Tarkanyi F, Hermanne A, Paviotti De Corcuera R (2003) Validation and upgrade of the recommended cross section data of charged particle reactions used for production pet radioisotopes. Nucl Instrum Meth B 211:169–189
Typ dokumentu
Bibliografia
Identyfikator YADDA
bwmeta1.element.baztech-article-BUJ8-0023-0025
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