Medical Radiology and Radiation Safety. 2015. Vol. 60. No. 4. P. 19-26

RADIATION SAFETY

A.S. Lunev, O.E. Klementyeva, G.E. Kodina

Computational Research of Prognosis Values of Absorbed Doses for Pre-Clinical Safety Evaluation of Radiopharmaceutical ⁶⁸Ga-Citrate

A.I. Burnasyan Federal Medical Biophysical Center of FMBA, Moscow, Russia, e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it.

ABSTRACT

Purpose: ⁶⁸Ga-citrate is a prospective radiopharmaceutical for PET-imaging of the inflammation. The use of radiopharmaceuticals is assumed with risk of various complications directly related to ionizing radiation. Therefore there is a need of the information on doses conducted to the pathological locus, organs and tissues and the whole organism in the process of the development and pre-clinical study of new radiopharmaceuticals. It is important for the safety assessment of radiopharmaceuticals.

Material and methods: ⁶⁸Ga-citrate is the object of the study. Nonlinear rats’ females (181.9 ± 16.0 g) with model of soft tissue inflammation conpose the study material. Absorbed and effective doses of ⁶⁸Ga-citrate were calculated in organs and tissues of rats according to the rats’ body distribution and extrapolated to human body.

Results: OLINDA/EXM 1.0 software was used for the calculation of doses. The highest absorbed doses were recorded as follows: 18.4 mGy in urinary bladder, 11.6 mGy in kidneys and 23.7 mGy in the intestine. Effective dose is 14.9 mSv. Such doses (less than 100 mSv) according ICRP and UNSCEAR publications should not be included in the irradiation damage assessment. Specific absorbed dose of the pathological area (model of aseptic inflammation) is 4.9 ± 4.3 mGy/MBq.

Conclusion: The results of dosimetry evaluation have determined the high safety level of ⁶⁸Ga-citrate radiopharmaceutical for PET-imaging of the inflammation.

Key words: ⁶⁸Ga-citrate, OLINDA/EXM 1.0 software, dosimetry

REFERENCES

1. Malakhovskii V.N., Trufanov G.E., Ryazanov V.V. Radiatsionnaya bezopasnost' pri radionuklidnykh issledovaniyakh. Saint Petersburg: Meditsina. 2008. P. 19-25.
2. Katz L., Penfold A.S. Range-energy relations for electrons and the determination of beta-ray endpoint energies by absorption. Rev. Mod. Phys. 1952. Vol. 52. No. 1. P. 28-35.
3. Buslenko N.P., Golenko D.I., Sobol I.M., et al. Metod statisticheskikh ispytanii (metod Monte-Karlo). Moscow, Gosudarstvennoe izdatel stvo fiziko-matematicheskoi literatury. 1962. 332 p.
4. Stepanenko V.F., Dedenkov A.N., Yas'kova E.K. et al. Avtomatizirovannaya sistema dozimetricheskikh raschetov pri razrabotkakh i ispytaniyakh novykh RFP i primenenii otkrytykh radionuklidov s diagnosticheskimi i lechebnymi tselyami. Med. radiol. 1988. Vol. 33. No. 2. P. 21-28.
5. Loevinger R., Budinger T., Watson E. MIRD primer for absorbed dose calculations. New York, Society of Nuclear Medicine. 1988.
6. International Commission on Radiological Protection. Recommendations of the International Commission on Radiological Protection. ICRP Publication 60, Pergamon Press. New York. 1991.
7. Stabin M.G. State of the art in nuclear medicine dose assessment. Sem. Nucl. Med. 2008. Vol. 38. No. 5. P. 308-320.
8. Stabin M.G., Siegel J.A. Physical models and dose factors for use in internal dose assessment. Health Phys. 2003. Vol. 85. No. 3. P. 294-306.
9. Skvortsov V.G., Orlov M.Yu., Petriev V.M. Biologicheskie i fiziko-dozimetricheskie issledovaniya novogo klassa radiofarmpreparatov na osnove generatornykh radionuklidov palladiya-103, reniya-188 i tekhnetsiya-99m. Biologiya i med. nauka. 2007. Vol. 4. P. 203-209.
10. Krasovskii G.N. Extrapolation of Experimental Data from animals to man. Environmental Health Perspectives. 1976. Vol. 13. No. 2. P. 51-58.
11. Kirschner A., Ice R., Beierwaltes W. Radiation dosimetry of ¹³¹I-19-iodocholesterol: the pitfalls of using tissue concentration data, the author’s reply. J. Nucl. Med. 1975. Vol. 16. No. 3. P. 248-249.
12. Tsan M.F. Mechanism of gallium-67 accumulation in inflammatory lesions. J. Nucl. Med. 1985. Vol. 26. No. 1. P. 88-92.
13. Publikatsiya 103 Mezhdunarodnoi Komissii po radiatsionnoi zashchite. Moscow, Alana. 2009. 344 p.
14. Mettler F.A., Walter H., Yoshizumi T.T., Mahesh M. Effective doses in radiology and diagnostic nuclear medicine. Radiology. 2008. Vol. 248. No. 1. P. 254-263.
15. Stabin M.G., Stubbs J B., Toohey R.E. Radiation Dose Estimates for Radiopharmaceuticals. — Oak Ridge: Institute for Science and Education. 1996. 98 p.
16. Lyra M. Radiation dosimetry in infection scintigraphic imaging. In: Radiopharmaceuticals for inflammations and infections. By Lyra M., Frantzis A., Limouris G. Athens. Mediterra Publishers. 2001. P. 117-128.

For citation: Lunev AS, Klementyeva OE, Kodina GE. Computational Research of Prognosis Values of Absorbed Doses for Pre-Clinical Safety Evaluation of Radiopharmaceutical ⁶⁸Ga-Citrate. Medical Radiology and Radiation Safety. 2015;60(4):19-26. Russian.

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