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Compact cyclotrons for the production of tracers and radiopharmaceuticals

Autorzy
Treść / Zawartość
Identyfikatory
Warianty tytułu
Konferencja
Proceedings of the XXXIII European Cyclotron Progress Meeting, 17-21 September 2002, Warszawa-Kraków, Poland
Języki publikacji
EN
Abstrakty
EN
Positron Emission Tomography (PET) is a method for determining biochemical and physiological processes in vivo in a quantitative manner. The most commonly used radionuclides are 11C, 13N, 15O and 18F, with respective half-lives of approximately 20 min, 10 min, 2 min, and 110 min. 18F labeled FDG (fluoro-2-deoxy-D-glucose) is now the most frequently used radiopharmaceutical and finds its application prominently in the field of oncology. Originally, the production of these radionuclides was performed with the existing accelerators, designed for nuclear physics, but with increasing interest in the PET methodology specially designed PET-production cyclotrons became available. The nuclear reactions involved are (p,n), (d,n), (p,a) and (d,a) and the thresholds for the nuclear reactions involved are 5 to 6 MeV. Based on these values and on other parameters, a proton 15 to 20 MeV cyclotron is often chosen. Since the half-life of a radionuclide limits the production time, the maximum beam current is an important parameter, together with the target construction, for the ultimate yield obtainable. In the development of special PET production cyclotrons, attention has also been paid to improve the extraction efficiency and the possibility of multiple extractions by designing negative ion cyclotrons. Commercial cyclotrons can often be acquired as an easy to operate integrated radionuclide production unit including targetry and some units. Regional FDG factories are nowadays being created to fulfil the demand for PET radiopharmaceutics. The possible choices in commercially available cyclotrons for the production of PET radionuclides will be discussed.
Czasopismo
Rocznik
Strony
169--172
Opis fizyczny
Bibliogr. 8 poz., rys.
Twórcy
autor
  • PET Center, Groningen University Hospital, Hanzeplein 1, 9713 GZ Groningen, P.O. Box 30.001, 9700 RB Groningen, The Netherlands, Tel.: +31 50/ 361 3311, Fax: +31 50/ 361 1687, a.m.j.paans@pet.azg.nl
Bibliografia
  • 1. Elsinga PH (2002) Radiopharmaceutical chemistry for positron emission tomography. Methods 27:208−217
  • 2. Friedlander G, Kennedy JW, Macias JM, Miller JM (1981) Nuclear radiochemistry, 3rd ed. John Wiley & Sons, New York
  • 3. Helus F (ed.) (1983) Radionuclides production. Vols 1−2. CRC Press, Boca Raton
  • 4. Hichwa RD, Nickles RJ (1979) The tuned pipeline − a link between small accelerators and nuclear medical needs. IEEE Trans Nucl Sci 26:1707−1709
  • 5. IAEA (2001) Charged particle cross-section database for medical radioisotope production: diagnostic radioisotopes and monitor reactions. TECDOC Series no. 1211. IAEA, Vienna
  • 6. Paans AMJ, van Waarde A, Elsinga PH, Willemsen ATM, Vaalburg W (2002) Positron emission tomography: the conceptual idea using a multidisciplinary approach. Methods 27:195−207
  • 7. Taylor LS (1977) Radiation protection design guidelines for 0.1−100 MeV particle accelerator facilities. Report no. 51. National Council on Radiation Protection and Measurements (NCRP)
  • 8. Thomas RH, Stevenson GR (1988) Radiological safety aspects of the operation of proton accelerators. TECDOC Series no 283. IAEA, Vienna
Typ dokumentu
Bibliografia
Identyfikator YADDA
bwmeta1.element.baztech-article-BUJ5-0004-0090
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