RESUMO
Separation of (90)Y from a parent solution of (90)Sr-(90)Y in 0.5 M nitric acid by two-stage liquid-liquid extraction has been investigated using centrifugal extractors. The extraction agent used was 0.25 M di-(2-ethylhexyl)phosphoric acid (D2EHPA) in n-dodecane. Back-extraction used 5 M HCl. Evaporation of HCl was performed in a rotary vacuum evaporator. Experience gained during the design, construction and running of more than 100 hot separations is presented. A short description of analytical methods used and results of the determination of chemical, radionuclidic and radiochemical purities and sterility are given.
Assuntos
Centrifugação , Medicina Nuclear , Compostos Radiofarmacêuticos/química , Ítrio/químicaRESUMO
ABSTRACT Particle emitting radionuclides (e.g. b--emitters 90Y and 177Lu, b-emitter 149Tb, Auger electron emitter 165Er or positron emitter 86Y) are more and more frequently used in research and clinical practice for imaging and radionuclide targeted therapy in nuclear medicine. These radiometals, altogether threevalent lanthanides or actinides with high specific radioactivity, coupled to biomolecule carriers (peptides or monoclonal antibodies) through chelating link (e.g. DTPA or DOTA) bind to specific antigens and/or receptors of diseased tissues, which enables the imaging (positron emitters) or destruction (b--, a-, and Auger electron emitter) of the diseased tissue releasing the antigens or carrying the receptors. The radionuclide precursor 90YCl3 (solution of hard b--emitter 90Y in diluted HCl) with high purity and specific activity is already commercially produced and succesfully used in nuclear medicine, e.g. for radioimmunotherapy (RIT) of Lymphoma. Specification and purity of our product obtained using extraction 90Sr/90Y generator (using technology of centrifuge extractors with di-2-ethylhexylphosphoric acid, D2EHPA) is examined and compared to other similar products in this contribution. A standard method for determination of labelling efficiency of the 90YCl3 precursor based on its reaction with DOTA-Tyr3-Octreotide (DOTA-TOC) and ITLC-SG chromatographic separation is described and proposed for the quality control.
Los radionucleidos emisores de partículas (ej. emisores b 90Y y 177Lu, emisores a 149Tb, emisor de electrones Auger 165Er o emisor de positrones 86Y) se emplean cada vez más en la investigación, en la práctica clínica para el procesamiento de imágenes y en la terapia dirigida de radionuclidos en medicina nuclear. Estos radiometales junto con actínidos o lantánidos trivalentes con alta actividad específica, asociados a portadores de biomoléculas (péptidos o anticuerpos monoclonales) por medio de un enlace con quelatos (ej. DTPA o DOTA) se unen a antígenos específicos receptores de tejidos afectados que permiten el procesamiento de imágenes (emisores de positrones) o la destrucción (b--, a-, y emisores de electrones de Auger) de los tejidos afectados que liberan los antígenos o portan los receptores. El precursor del radionucleido 90YCI3 (solución de emisor b- duro - 90Y en HCI diluido) con elevada pureza y actividad específica ya se produce comercialmente y se usa exitosamente en la medicina nuclear, por ejemplo, para la radioinmunoterapia (RIT) del linfoma. En esta contribución se examina la especificación y la pureza de nuestro producto, obtenido mediante extracción con generador 90Sr/90Y (empleando la tecnología de extractores por centrifugado con ácido di-2-ethylhexyl phosphoric D2EHPA) y se compara con otros productos similares. Se describe y propone para el control de la calidad un método estándar para determinar la eficiencia en el marcaje del precursor del 90YCI3 basado en su reacción con DOTA-Tyr3-ostreotido (DOTA-TOC) y separación cromatográfica ITLC-SG.
RESUMO
(166)Ho is a beta-emitter (E(_max) = 1.84 MeV, T1/2 = 26.7 hours) with a mean penetration in the soft tissue of 2.2 mm and gamma-photons 81keV and 1380keV. In this paper, we present our experiences with preparation of (166)Ho-macroaggregates ((166)Ho-MA) for radiosynoviorhesis. Ho-MA were prepared by reacting the aqueous solution of holmium nitrate pentahydrate with sodium borohydride solution in 0.2 M NaOH. After centrifugation, washing, and drying at 105 degrees C, final fineness of 1-15 microm was attained using a homogenizer working at 70,000 rpm. Neutron activation was carried out in screwed titanium ampules in a nuclear reactor at the neutron flux 10E12-10E14 neutrons.cm-24.s-1. The irradiated samples were allowed to cool 24 hours before further manipulation. (166)Ho-MA were clinically tested on 20 patients suffering from gonarthrosis (15), rheumatoid arthritis (5), psoriatic arthritis (1), and gout arthropathy (1). (166)Ho-MA are currently produced under GMP and production facility allows producing radioactivity for 6 patients within one production run.
