Radiochemical separation of 224Ra from 232U and 228Th sources for 224Ra/212Pb/212Bi generator.

The application of diagnostic and therapeutic radionuclides in nuclear medicine has grown significantly and has translated into the increased interest in radionuclide generators and their development. 224Ra and its shorter-lived daughters, 212Pb and 212Bi, are very interesting radionuclides from Targeted Alpha Therapy point of view for treatment of small cancers or metastatic forms. The purpose of the present work was to develop a simple generator for rapid elution of carrier-free 224Ra from 232U or 228Th sources by radiochemical separation based on extraction chromatography with the utilization of a home-made material. The bis(2-ethylhexyl) hydrogen phosphate (HDEHP) extractant was immobilized on polytetrafluroethylene (PTFE) grains and its ability to selectively adsorb 232U and 228Th, with simultaneous high elution recovery of 224Ra, was checked over few years. The 224Ra was quantitatively eluted with small volume (3-5 mL) of 0.1 M HNO3 with low breakthrough (<0.005%) and was used for further milking of 212Bi and 212Pb from DOWEX 50WX12 by 0.75 M and 2.0 M HCl, respectively. The elaborated here methods allowed high recovery of 224Ra, 212Pb and 212Bi radionuclides and their application in radiolabeling of various biomolecules.

Facile Chip-Based Array Monolithic Microextraction System Online Coupled with ICPMS for Fast Analysis of Trace Heavy Metals in Biological Samples.

Trace heavy metals have great impact on biological system; therefore, it is essential to develop suitable analytical methods for the determination of trace heavy metals in biological samples to elucidate their biochemical and physiological functions in organisms. Herein, we presented a chip-based array monolithic microextraction system and combined it with inductively coupled plasma mass spectrometry (ICPMS) for online analysis of trace Hg, Pb, and Bi in real-world biological samples. Six ethylenediamine modified poly(glycidyl methacrylate-co-ethylene glycol dimethacrylate) (poly(GMA-co-EDMA-NH2)) capillary monolithic columns were embedded parallelly in microchannels of a microfluidic chip for array monolithic microextraction. Various parameters affecting the chip-based array monolithic microextraction of target metals were investigated. The sample throughput of the proposed method was 16 h-1, with the limits of detection for Hg, Pb, and Bi of 23, 12, and 13 ng L-1, respectively. The developed method was validated by the determination of trace Hg, Pb, and Bi in HepG2 cells and human urine samples, and the recoveries for the spiked samples were in the range of 90.4-102%. This chip-based array monolithic microextraction system is easy to prepare, and the proposed online analytical system provides a new platform for trace elements analysis in biological samples with the merits of high sample throughput, high sensitivity, and low sample/reagents consumption.

Bismuth-213 and actinium-225 -- generator performance and evolving therapeutic applications of two generator-derived alpha-emitting radioisotopes.

The alpha emitters (225)Ac and (213)Bi are promising therapeutic radionuclides for application in targeted alpha therapy of cancer and infectious diseases. Both alpha emitters are available with high specific activity from established radionuclide generators. Their favourable chemical and physical properties have led to the conduction of a large number of preclinical studies and several clinical trials, demonstrating the feasibility, safety and therapeutic efficacy of targeted alpha therapy with (225)Ac and (213)Bi. This review describes methods for the production of (225)Ac and (213)Bi and gives an overview of (225)Ac/(213)Bi radionuclide generator systems. Selected preclinical studies are highlighted and the current clinical experience with (225)Ac and (213)Bi is summarized.

Breakthrough of 225Ac and its radionuclide daughters from an 225Ac/213Bi generator: development of new methods, quantitative characterization, and implications for clinical use.

Bisumth-213, a short-lived alpha particle emitting radionuclide, is generated from the decay of 225Ac, which has a half-life of 10 days. The development of a clinical 225Ac/213Bi generator and the preparation of a 213Bi radiolabeled antibody for radioimmunotherapy of leukemia have been reported. The 225Ac decay scheme is complex; therefore a thorough understanding of the impact of both the parent 225Ac and its daughters on radiolabeling, purification, and quantification is necessary for optimal use of the generator system. This paper reports: (i) unique new methods to measure 221Fr, 213Bi, and 209Pb, the prominent daughters of 225Ac; and (ii) a quantitative evaluation of 225Ac/213Bi generator breakthrough and the radionuclidic purity of 213Bi labeled radiopharmaceutical dose formulations. A quantitative multi-dimensional proportional scanning method was employed to distinguish and measure specific daughter radionuclides. This method combines thin layer chromatography in two perpendicular directions with attenuated collimation as a function of time for data collection and analysis. Francium-221 and 213Bi eluted differentially from the generator, and 221Fr contributed minimally to unchelated 213Bi in the reaction and final products. Lead-209 was present in the reaction solution, but not strongly bound by the chelating moiety either (i) under the 213Bi labeling reaction conditions or (ii) following chelated 213Bi decay. As a consequence of incorporating several new procedures to the operation of the generator, 225Ac breakthrough in the final product was further reduced and represented a trivial contaminant in the final drug formulations.

Rapid preparation of short-lived alpha particle emitting radioimmunopharmaceuticals.

Alpha emitting radionuclides are of considerable interest for targeted radioimmunotherapy. Generator supplied 213Bi emitting 8.5 MeV alpha particles with a 45.6 min half-life has been conjugated to a monoclonal antibody (HuM195-CHX-A-DTPA) for targeted therapy of leukemia in a clinical trial. The clinical dose preparation of pharmaceutical formulation by a pair of skilled radiochemists took 25 min, which corresponds, to an overall decay loss of 30% of the initial 213Bi activity eluted from the generator. In order to allow more widespread and practical clinical use of targeted 213Bi alpha particle therapy, we developed a new procedure that is simpler, more rapid and adaptable to a hospital pharmacy. The new 10 min process includes a tandem elution and labeling, and an anion exchange column purification method that can be reproducibly used.

Evaluation of an internal cyclotron target for the production of 211At via the 209Bi (alpha,2n)211 at reaction.

Astatine-211 is a 7.2 h half-life alpha-emitting radionuclide which has shown great promise for targeted radiotherapy. It is generally produced by cyclotron bombardment of bismuth metal targets with 28 MeV alpha-particles via the 209Bi(alpha,2n)211 At reaction. In order to provide 211At activity levels anticipated for clinical investigations, an internal target system has been designed and evaluated. The system has a grazing-angle configuration and leading- and trailing-edge monitors. Both aluminum and copper target backings were evaluated. With approx. 28 MeV alpha-particles, the 211At production efficiency was 41 +/- 7 MBq/microA.h, compared with 10.6 +/- 1.2 MBq/microA.h for an external target. Radionuclidic purity of 211At was high with no evidence of 210At.