At Legnaro laboratories of the Italian National Institute for Nuclear Physics (INFN), a feasibility study has started since 2011 related to accelerated-based direct production of by the 100Mo(p,2n) reaction. Both theoretical investigations and some recent preliminary irradiation tests on 100Mo-enriched samples have pointed out that both the / ratio and the specific activity will be basically different in the final accelerator-produced Tc with respect to generator-produced one, which might affect the radiopharmaceutical procedures. The aim of this work was to evaluate the possible impact of different / isomeric ratios on the preparation of different Tc-labeled pharmaceutical kits. A set of measurements with , eluted from a standard 99Mo/ generator, was performed, and results on both radiochemical purity and stability studies (following the standard quality control procedures) are reported for a set of widely used pharmaceuticals (i.e., -Sestamibi, -ECD, -MAG3, -DTPA, -MDP, -HMDP, -nanocolloids, and -DMSA). These pharmaceuticals have been all reconstituted with either the first [ O4]？ eluate obtained from a 99Mo/ generator (coming from two different companies) or eluates after 24, 36, 48, and 72 hours from last elution. Results show that the radiochemical purity and stability of these radiopharmaceuticals were not affected up to the value of 11.84 for the / ratio. 1. Introduction 99mTc, with its peculiar physical-chemical properties, still continues to be the most important radionuclide used in diagnostic nuclear medical procedures. In particular, the developments of technetium chemistry have opened new perspectives in the field of diagnostic imaging [1]. More than 80% of the radiopharmaceuticals are currently labeled with this radionuclide [1] by reconstitution with sodium pertechnetate [2–4] [Na99mTcO4] commercial kits containing in lyophilized form the various reagents required for the preparation of each radiopharmaceutical. Its routine applications are ensured by the availability of portable 99Mo/99mTc generators in which 99Mo is bound as molybdate anion to alumina columns. Current global interruptions of 99Mo supply that involved uranium fission of highly enriched 235U targets, aging reactors, and the staggering costs of their maintenance, focused on the search for alternative method of the 99mTc production [5]. One of the possibilities is to replace the reactors with particle accelerators, aiming at a regional production and distribution. At Legnaro laboratories of the Italian National Institute for Nuclear Physics (INFN), a feasibility study
References
[1]
S. Banerjee, M. R. Ambikalmajan Pillai, and N. Ramamoorthy, “Evolution of Tc-99m in diagnostic radiopharmaceuticals,” Seminars in Nuclear Medicine, vol. 31, no. 4, pp. 260–277, 2001.
[2]
O. P. D. Noronha, A. B. Sewatkar, and R. D. Ganatra, “Fission produced 99Mo- generator system for medical use,” Journal of Nuclear Biology and Medicine, vol. 20, no. 1, pp. 32–36, 1976.
[3]
N. Vinberg and K. Kristensen, “Fission Mo-99/Tc-99m generators—a study of their performance and quality,” European Journal of Nuclear Medicine, vol. 5, no. 5, pp. 435–438, 1980.
[4]
J. Vucina, “Technetium-99m production for use in nuclear medicine,” Medicinski Pregled, vol. 53, no. 11-12, pp. 631–634, 2000.
[5]
N. Knight, “Return of the radionuclide shortage,” Journal of Nuclear Medicine, vol. 50, no. 7, pp. 13N–14N, 2009.
[6]
J. Esposito, “Feasibility study report on alternative 99Mo/ production routes using particle accelerators at LNL, (2001 version),” INFN-LNL-235, 2011.
[7]
Report on the 1st Research Coordination Meeting of IAEA CRP Activities (code F22062), “Accelerator-based Alternatives to Non-HEU Production of 99Mo/ ,” Vancouver, Canada, April 2012.
[8]
J. L. Vucina, “Radionuclide purity of eluate for use in nuclear medicine,” Medicinski Pregled, vol. 49, no. 1-2, pp. 41–44, 1996.
[9]
D. M. Hill, R. K. Barnes, H. K. Y. Wong, and A. W. Zawadzki, “The quantification of technetium in generator-derived pertechnetate using ICP-MS,” Applied Radiation and Isotopes, vol. 53, no. 3, pp. 415–419, 2000.
[10]
J. Bonnyman, “Effect of milking efficiency on 99Tc content of derived from generators,” International Journal of Applied Radiation and Isotopes, vol. 34, no. 6, pp. 901–906, 1983.
[11]
M. Marengo, C. Aprile, C. Bagnara et al., “Quality control of 99Mo/ generators: results of a survey of the radiopharmacy working group of the Italian Association of Nuclear Medicine (AIMN),” Nuclear Medicine Communications, vol. 20, no. 11, pp. 1077–1084, 1999.
[12]
M. M. Webber, M. D. Cragin, and W. K. Victery, “Aluminum content in eluents from commercial technetium generators,” Journal of Nuclear Medicine, vol. 12, no. 10, p. 700, 1971.
[13]
A. M. Zimmer and D. G. Pavel, “Rapid miniaturized chromatographic quality-control procedures for Tc-99m radiopharmaceuticals,” Journal of Nuclear Medicine, vol. 18, no. 12, pp. 1230–1233, 1977.
A. Hammermaier, E. Reich, and W. Bogl, “Chemical, radiochemical, and radionuclide purity of eluates from different commercial fission 99Mo/ generators,” European Journal of Nuclear Medicine, vol. 12, no. 1, pp. 41–46, 1986.
[16]
P. Nasman and T. Vayrynen, “Impurities of -generators,” European Journal of Nuclear Medicine, vol. 8, no. 1, pp. 26–29, 1983.
[17]
T. Vayrynen, P. Nasman, and K. Kiviniitty, “Residual activity of Tc-generators,” European Journal of Nuclear Medicine, vol. 6, no. 6, pp. 269–271, 1981.
[18]
S. Hoory, D. Bandyopadhyay, J.-C. Vaugeois, and L. M. Levy, “Impurities in generator eluates and radiopharmaceuticals: a computerized quality assurance approach,” Health Physics, vol. 50, no. 6, pp. 843–848, 1986.
[19]
“Radiopharmacy and quality control pharmacists subcommittees of the regional pharmaceutical officers commitee. Quality assurance of radiopharmaceuticals,” Nuclear Medicine Communication, vol. 15, pp. 886–889, 1994.
[20]
E. M. Podolak Jr., “134Cs, 86Rb, and 60Co in 99Mo- generator eluate,” Journal of Nuclear Medicine, vol. 13, no. 6, pp. 388–390, 1972.
[21]
I. Zolle, Technetium-99m Pharmaceuticals: Preparation and Quality Control in Nuclear Medicine, Springer, Berlin, Germany, 2007.
[22]
A. Del Guerra, A. Bartoli, N. Belcari et al., “Performance evaluation of the fully engineered YAP-(S)PET scanner for small animal imaging,” IEEE Transactions on Nuclear Science, vol. 53, no. 3, pp. 1078–1083, 2006.
