Samarium-153 EDTMP for metastatic bone pain palliation: The impact of europium impurities

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.

Dosimetric implications of the potential radionuclidic impurities in 153Sm-DOTMP

Thehuman internal dosimetry of the radionuclidic impurities of samarium-153 in a new bone-seeking radiopharmaceutical, ¹⁵³Sm-1,4,7,10tetraazacyclododecanetetramethylenephosponic acid (¹⁵³Sm-DOTMP), has been estimated from preclinical data. The effective dose from the impurities in lower-specific-activity ¹⁵³Sm is less than 17% of the effective dose from pure Sm-153. It has a background-equivalent radiation time for a dosage of 37 MBq/kg of less than one-half year.

Development of neutron-activated samarium-153-loaded polystyrene microspheres as a potential theranostic agent for hepatic radioembolization

PURPOSE

Hepatic radioembolization is an effective minimally invasive treatment for primary and metastatic liver cancers. Yttrium-90 [90Y]-labelled resin or glass beads are typically used as the radioembolic agent for this treatment; however, these are not readily available in many countries. In this study, novel samarium-153 oxide-loaded polystyrene ([153Sm]Sm2O3-PS) microspheres were developed as a potential alternative to 90Y microspheres for hepatic radioembolization.

METHODS

The [152Sm]Sm2O3-PS microspheres were synthesized using solid-in-oil-in-water solvent evaporation. The microspheres underwent neutron activation using a 1 MW open-pool research reactor to produce radioactive [153Sm]Sm2O3-PS microspheres via 152Sm(n,γ)153Sm reaction. Physicochemical characterization, gamma spectroscopy and in-vitro radionuclide retention efficiency were carried out to evaluate the properties and stability of the microspheres before and after neutron activation.

RESULTS

The [153Sm]Sm2O3-PS microspheres achieved specific activity of 5.04 ± 0.52 GBq·g-1 after a 6 h neutron activation. Scanning electron microscopy and particle size analysis showed that the microspheres remained spherical with an average diameter of ~33 μm before and after neutron activation. No long half-life radionuclide and elemental impurities were found in the samples. The radionuclide retention efficiencies of the [153Sm]Sm2O3-PS microspheres at 550 h were 99.64 ± 0.07 and 98.76 ± 1.10% when tested in saline solution and human blood plasma, respectively.

CONCLUSIONS

A neutron-activated [153Sm]Sm2O3-PS microsphere formulation was successfully developed for potential application as a theranostic agent for liver radioembolization. The microspheres achieved suitable physical properties for radioembolization and demonstrated high radionuclide retention efficiency in saline solution and human blood plasma.

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.

Knee radiosynovectomy with 153Sm-hydroxyapatite compared to 90Y-hydroxyapatite: initial results of a prospective trial

INTRODUCTION

Radiosynovectomy (RS) with ⁹⁰Y-hydroxyapatite (⁹⁰Y-HyA) aims to control knee hemarthrosis in hemophiliac patients to prevent secondary arthropathy. However, knee RS using ¹⁵³Sm-hydroxyapatite (¹⁵³Sm-HyA) is considered less suitable due to the lower average soft tissue range and energy of ¹⁵³Sm for large joints, such as the knees.

PURPOSE

The objective of this investigation was to assess the efficacy and safety of knee RS with ¹⁵³Sm-HyA, compared to ⁹⁰Y-HyA.

METHODS

Forty patients were prospectively assigned to undergo knee RS with ¹⁵³Sm-HyA (n = 19) or with ⁹⁰Y-HyA (n = 21). The frequency of hemarthrosis episodes before and after treatment were compared.

RESULTS

After six months of knee RS, ¹⁵³Sm-HyA and ⁹⁰Y-HyA promoted a similar reduction of hemarthrosis episodes (50% and 66.7%, respectively). However, after 12 months of knee RS, the reduction of hemarthrosis episodes was significantly (p = 0.037) higher using ¹⁵³Sm-HyA (87.5%) compared to ⁹⁰Y-HyA (50.0%). This discrepancy was more pronounced (p = 0.002) for ¹⁵³Sm-HyA compared to ⁹⁰Y-HyA in adults/adolescents.

CONCLUSION

Knee radiosynovectomy with ¹⁵³Sm-HyA is safe, reduces hemarthrosis episodes after 12 months of treatments, especially in adults/adolescents and even with grades III/IV arthropathy, similar to ⁹⁰Y-HyA. ⁹⁰Y-HyA seems to promote better hemarthrosis control in small children.

Separation of samarium and europium by solvent extraction with an undiluted quaternary ammonium ionic liquid: towards high-purity medical samarium-153

Long-lived europium-154 impurities are formed during the production of medical samarium-153 in a high-flux nuclear reactor. A method to separate these europium impurities from samarium was investigated using the hydrophobic quaternary ammonium ionic liquid Aliquat 336 nitrate. The separation method consists of the selective reduction of Eu3+ by zinc metal in an aqueous feed solution containing a high nitrate salt concentration. Subsequent extraction using undiluted Aliquat 336 nitrate leads to an efficient separation of both lanthanides in a relatively short time frame. Sm3+ was extracted to the neat ionic liquid phase much more efficiently than Eu2+. An initial approach using the addition of dicyclohexano-18-crown-6 to capture Eu2+ in the ionic liquid phase was less efficient.