The development and use of radionuclide generators in nuclear medicine -- recent advances and future perspectives

Abstract

This is a preprint of a paper intended for presentation at a scientific meeeting. Because of the provisional nature of its content and since changes of substance or detail may have 10 be made before publication, the preprint is made available on the understanding that it will not be cited in the literature or in any way be reproduced in its present form. The view expressed and the Statements made remain the responsibility of the named author(s); the views do not necessarily reflect those of the government of the designating Member State(s) or of the designating organization(s). In particular. neither rhe lAEA nor any other organization or body sponsoring this meeting can be held responsible for any material reproduced in this preprint. DISCLAIMERThis report was prepared as an account of work sponsored by an agency of the United States Government Neither the United States Government nor my agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any spccific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise docs not necessarily constitute or imply its endorsement, m o mmendation, or favoring by the United States Govcnrment or any agency thereof.The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or.any agency thereof.. ABSTRACT 2Although the trend in radionuclide generator research has declined (FIG. 1 ), radionuclide generator systems continue to play an important role in nuclear medicine [l-31. obtained from the molybdenum-99/technetium-99m generator system is used in over 80 per cent of all diagnostic clinical studies and there is increasing interest and use of therapeutic radioisotopes obtained from generator systems. This paper focuses on a discussion of the major current areas of radionuclide generator research, and the expected areas of future research and applications. 1.The Molydenum-99/Technetium-99rn GeneratorThe easiest and preferred route for obtaining technetium-99m for radiopharmaceutical "kit" labeling is via elution of the chromatographic-type molybdenum-99/technetium-99m generator.Because technetium-99mis expected to continue to be the primary radioisotope used for imaging in diagnostic clinical nuclear medicine, the availability of molybdenum-99 is crucial to the radiopharmaceutical and clinical communities. In the more developed countries, fission-produced molybdenum-99 for is used for fabrication of the chromatographic-type molybdenum-99/technetium-99m generator [4]. Although until recently only one site provided most of the fission-produced molybdenum-99 for generator fabrication in North America, there are currently several new sites throughout the world producing this important radioisotope ( Table 1). Wit...

TcGenerator Development: Up-to-DateTcRecovery Technologies for Increasing the Effectiveness ofLe1 2014Science and Technology of Nuclear Installations16080View full textAdd to dashboardCite

“…So, the radioisotope concentrator device should be developed to increase the concentration and quality of injectable 99m Tc eluates and consequently the generator life time or the effectiveness of the generator utilisation. Some concentration methods have been developed for increasing 99m Tc concentration of the saline eluate for extension of the life time of the fission- 99 Mo-based 99m Tc generators [38][39][40][41][42][43][44]. All these methods used a chloride-removing column containing Ag+ ions, which couple with a pertechnetate-concentrating sorbent column such as alumina, Bonelut-SAX, QMA, and multifunctional sorbent.…”

“…Several research groups reported on using different nonsaline aqueous eluents for elution of 99m Tc from alumina-based generator systems which couple with a concentration unit for increasing the pertechnetate concentration of the 99m Tc solution. The eluents used are the following: the mixture of 0.7 M acetic acid and 0.0225 M NaCl solution [50], the solution of the salt of weak acids such as ammonium acetate, citrate, titrate, and so forth, and the mixture of acetic acid and ammonium acetate solution [43][44][45][46][47][48]. Although the elution performance of these eluents is excellent and suitable for the concentration processes using an anion exchange materials such as QMA Sep-Pak Cartridge, NH 2 Amberlite, BondElut SAX, Dowex-1, DEAE Cellulose, and so forth, the large volume of the eluents used for the 99m Tc elution from large alumina column-based generators is the main issue for the routine use of all these methods.…”

Estudos de técnicas de concentração da atividade de 99mTc eluído de geradores de 99Mo/99mTc tipo gel

“…TABELA 3 -Isótopos radioativos de rênio [52] . [58,59] . FIGURA 8 -Esquema detalhado de funcionamento do sistema de concentração com trocadores catiônico/aniônico em série eluído com acetato de amônio 0,3 mol.L -1 [58,59] .…”

“…Boyd [25] , em 1997, citou uma técnica de concentração para o gerador de FIGURA 13 -Esquema detalhado de funcionamento do sistema de concentração com trocadores catiônico/aniônico em série eluído com solução de NaCl 0,9 % [58,59] . FIGURA 14 -Gerador com coluna de alumina ácida "jumbo" (40 g, 20x90 mm) acoplada a um sistema de concentração com coluna aniônica DEAE celulose [17] .…”

“…A retenção de 99m Tc pela coluna de alumina foi maior que 90 % e o fator de concentração do sistema foi de 4. Mushtaq et al [64] , relataram o uso de uma mistura de ácido acético 0,7 mol.L -1 e solução de NaCl 0,0225 mol.L -1 como eluente do gerador cromatográfico 99 Mo/ 99m Tc a base de alumina e usando como sistema de concentração um cartucho aniônico (QMA -Waters), mesmo sistema adotado por Knapp(1998). A metodologia deste sistema de concentração é o mesmo descrito no ítem 1.9.1 para o 188 Re.…”