An electrochemical approach for removal of radionuclidic contaminants of Eu from 153 Sm for effective use in metastatic bone pain palliation

Emerging role of electrochemistry in radiochemical separation of medically important radiometals: state of the art

Electrochemical separation technology has brought a renaissance in the field of nuclear medicine towards obtaining clinical-grade radiometals for preparation of a wide variety of radiopharmaceuticals. This article is a comprehensive summary of the electrochemical processes developed for the separation of radiometals that could be used for diagnostic or therapeutic applications in nuclear medicine. For using electrochemistry as a tool for the separation of radiometals, intricate knowledge is essential to understand the basic parameters of electrochemical separation processes which include applied potential, selection of electrolyte, choice of the electrode, the temperature of the electrolyte, pH of the electrolyte and time of electrolysis. The advantages of the electrochemical separation approach over the other conventional methodologies such as solvent extraction, column chromatography, sublimation, etc., have also been discussed. The latest research and development from our laboratory on electrochemical methodologies developed for separation of 90Y from 90Sr, 188Re from 188W, 99mTc from 99Mo, 47Sc from 46Ca, 45Ca from 46Sc,153Sm from 154Eu, 169Er from 169Yb, 177Lu from Yb and 132/135La from Ba have been described. In all the cases, the final product is obtained either in a 'no-carrier-added' (NCA) form or free from inextricable impurities and thus found suitable for formulation of radiopharmaceuticals.

Cutting edge rare earth radiometals: prospects for cancer theranostics

Background

With recent advances in novel approaches to cancer therapy and imaging, the application of theranostic techniques in personalised medicine has emerged as a very promising avenue of research inquiry in recent years. Interest has been directed towards the theranostic potential of Rare Earth radiometals due to their closely related chemical properties which allow for their facile and interchangeable incorporation into identical bifunctional chelators or targeting biomolecules for use in a diverse range of cancer imaging and therapeutic applications without additional modification, i.e. a “one-size-fits-all” approach. This review will focus on recent progress and innovations in the area of Rare Earth radionuclides for theranostic applications by providing a detailed snapshot of their current state of production by means of nuclear reactions, subsequent promising theranostic capabilities in the clinic, as well as a discussion of factors that have impacted upon their progress through the theranostic drug development pipeline.

Main body

In light of this interest, a great deal of research has also been focussed towards certain under-utilised Rare Earth radionuclides with diverse and favourable decay characteristics which span the broad spectrum of most cancer imaging and therapeutic applications, with potential nuclides suitable for α-therapy (¹⁴⁹Tb), β⁻-therapy (⁴⁷Sc, ¹⁶¹Tb, ¹⁶⁶Ho, ¹⁵³Sm, ¹⁶⁹Er, ¹⁴⁹Pm, ¹⁴³Pr, ¹⁷⁰Tm), Auger electron (AE) therapy (¹⁶¹Tb, ¹³⁵La, ¹⁶⁵Er), positron emission tomography (⁴³Sc, ⁴⁴Sc, ¹⁴⁹Tb, ¹⁵²Tb, ¹³²La, ¹³³La), and single photon emission computed tomography (⁴⁷Sc, ¹⁵⁵Tb, ¹⁵²Tb, ¹⁶¹Tb, ¹⁶⁶Ho, ¹⁵³Sm, ¹⁴⁹Pm, ¹⁷⁰Tm). For a number of the aforementioned radionuclides, their progression from ‘bench to bedside’ has been hamstrung by lack of availability due to production and purification methods requiring further optimisation.

Conclusions

In order to exploit the potential of these radionuclides, reliable and economical production and purification methods that provide the desired radionuclides in high yield and purity are required. With more reactors around the world being decommissioned in future, solutions to radionuclide production issues will likely be found in a greater focus on linear accelerator and cyclotron infrastructure and production methods, as well as mass separation methods. Recent progress towards the optimisation of these and other radionuclide production and purification methods has increased the feasibility of utilising Rare Earth radiometals in both preclinical and clinical settings, thereby placing them at the forefront of radiometals research for cancer theranostics.

[Evaluation of radionuclide impurities in several radiopharmaceuticals]

PURPOSE

Revisions to German radiation protection laws have resulted in updated limit values, which could affect the unrestricted release of waste produced by nuclear medicine therapy. In addition, signs of long-lived concomitant nuclides in ¹⁵³Sm and ²²³Ra radiopharmaceuticals have been seen in the past. Therefore, the goal of this article was to analyze the radionuclidic purity of selected radiopharmaceuticals.

METHOD

48 samples from 12 different radiopharmaceuticals were examined. A high purity germanium semiconductor detector (HPGe detector) was used for the qualitative and quantitative evaluation of concomitant nuclides.

RESULTS

Various europium isotopes were identified in ⁹⁰Y-citrate, ¹⁵³Sm-Quadramet, ¹⁶⁶Ho-QuiremSpheres, and ¹⁶⁹Er-erbium citrate, with the greatest amount being found in ¹⁵³Sm (7.0 ppm (¹⁵²Eu), 8.4 ppm (¹⁵⁴Eu), and 2.1 ppm (¹⁵⁵Eu)). ¹⁶⁹Yb was the most significant impurity in ¹⁶⁹Er (513 ppm). In the case of ¹⁷⁷Lu radiopharmaceuticals, there was a significant difference in the ^177mLu content (0.8 ppm vs. 0.0024 ppm) between two different manufacturers. No concomitant nuclides could be found within the detection limits in the case of ⁹⁰Y spheres, ²²³Ra, and ²²⁵Ac.

CONCLUSION

The limit values for unrestricted release are exceeded manyfold in the case of the identified concomitant nuclides. As a result, alternative release procedures (extension of the decay time, specific release, release in the individual case) or transfer to collection facilities must be considered. Technical methods for reducing or preventing impurities could also be a possible solution. Consequences for patient radiation exposure were able to be ruled out.

The radio-europium impurities in [153Sm]-EDTMP production: a review of isolation methods

Many human cancers predominantly metastasize to the bone which causes bone pain and other symptoms. However, the management of bone metastases is challenging. Radionuclide therapy using low-energy beta-emitting radionuclides has yielded encouraging results. The aim of this therapy is to deliver the maximum dose to the metastatic sites but a minimal dose to the normal tissue. Samarium-153 [153Sm]Sm-Ethylenediamine tetramethylene phosphonate (EDTMP) is an FDA and European Medicine Agency approved (Quadramet) radionuclide and is widely used for bone pain palliation. 153Sm is reactor produced, and the presence of europium impurities is thus unavoidable. This in turn causes an increase in the hospital radioactive waste burden and in radiation absorbed doses to the patients, and therefore it is a concern. The effective removal of these impurities is thus highly desirable before its administration to the patients. In this article, we present a detailed review of the various methods described in the literature for separation of 153Sm and Eu, that is solvent extraction, ion-exchange chromatography, electrochromatography, electrochemical separation and supported ionic liquid phase.

Facile radiochemical separation of clinical-grade 90Y from 90Sr by selective precipitation for targeted radionuclide therapy

INTRODUCTION

The widespread clinical utilization of ⁹⁰Y for preparation of target specific radiopharmaceuticals demands development of a facile, efficient and cost-effective method for radiochemical separation of ⁹⁰Y from ⁹⁰Sr via⁹⁰Sr/⁹⁰Y generator. In this article, we describe an efficient and facile method for radiochemical separation of ⁹⁰Y from ⁹⁰Sr for preparation of radiopharmaceuticals by exploiting the large difference in the solubility product constants (K_sp) of Y(OH)₃ and Sr(OH)₂.

METHODS

A two-step radiochemical separation procedure based on selective precipitation of ⁹⁰Y under alkaline conditions from ⁹⁰Sr/⁹⁰Y equilibrium mixture was developed. The ⁹⁰Y(OH)₃ colloid formed at pH ~ 10 was selectively trapped in 0.22 μm sterile filter and was subsequently retrieved by dissolution in HCl solution. Detailed quality control analyses of obtained ⁹⁰Y were carried out and its utility towards preparation of different radiopharmaceuticals was assessed.

RESULTS

Using the same feed solution of ⁹⁰Sr (3.7 GBq), consistent and repeated separation of ⁹⁰Y could be achieved in different batches with >85% yield and >99.999% radionuclidic purity. Yttrium-90 obtained from this process was found suitable for preparation of therapeutically relevant doses of three different radiopharmaceutical formulations, namely, ⁹⁰Y-DOTA-TATE, ⁹⁰Y-PSMA-617 and ⁹⁰Y-CHX-A″-DTPA-Cetuximab with >95% radiochemical purity.

CONCLUSIONS

The promising results obtained in this study would facilitate implementation of the developed technique for obtaining ⁹⁰Y in adequate quantity and of required purity from a centralized radiopharmacy setup.