Radionuclide production for therapeutic radiopharmaceuticals

Half-life determination of 111Ag

¹¹¹Ag is a radionuclide that can be generated by neutron capture on ¹¹⁰Pd and whose decay properties and production feasibility make it a potential therapeutic agent against arthritis. Due to the discrepancies of recent published values of the half-life of ¹¹¹Ag with previous published works which are not thoroughly documented for detailed experiment procedures and uncertainty budgets evaluation, an independent redetermination of the ¹¹¹Ag half-life value is required. In this work, a solid ¹¹¹Ag source was prepared and repeatedly measured in a high purity Germanium (HPGe) detector to determine its half-life. In total, more than fifty measurements were performed over a period of 26.3 days, corresponding to ∼3.5 half-lives of ¹¹¹Ag. The experimental method and corresponding uncertainty budget are presented. The result of 7.419(15) days is consistent with the recently published value, 7.423(13) days, by Collins et al. and deviates by 0.418% from the currently recommended value 7.45(1) days. A new recommend half-life value of 7.437(7) days was determined utilizing all available experimental values by a power-moderated mean (PMM) method.

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.

Effects of deuteron optical models on the cross-section calculations of deuteron induced reactions on natural germanium

A common feature of scientific studies is that when experimental observation data are not available, theoretical calculations are used to obtain information about the subject under investigation. In this context, many parameters and theoretical models have been developed that can be used in nuclear physics studies just as it is in other branches of sciences. It is intended that by doing so, theoretical models can be improved using recent experimental data while also learning about outcomes where experimental data is unavailable or difficult to access. Among the many theoretical models available, there are also deuteron optical models whose effects are examined in this study. The objective of this study is to examine the effects of different deuteron optical models on the cross-section calculations of deuteron induced reactions on natural germanium. The cross-section values of ^natGe(d,x)⁷⁰As, ^natGe(d,x)⁷¹As, ^natGe(d,x)⁷²As, ^natGe(d,x)⁷³As, ^natGe(d,x)⁷⁴As and ^natGe(d,x)⁷⁶As reactions were calculated using five deuteron optical models in the TALYS code's v1.95 for this aim, and the results were compared to the experimental data available in the database known as Experimental Nuclear Reaction Data (EXFOR) library. Graphics and quantitative analyses were also used to present the findings and interpretations of the outcomes.

Efficient trace-scale extraction method of reactor produced 199Au adequate for nuclear medicine applications

Production of no carrier-added (NCA) 199Au through natPt(n, γ) reaction and subsequent purification using liquid-liquid extraction from other radioisotopes is studied in the context of theranostic application. Comparative separation of NCA 199Au after dissolution of activated Pt target using three Cyanex compounds (Cyanex-272, Cyanex-302 and Cyanex-923) is evaluated. The extraction process is optimized in terms of the type of extractant, the concentration of extractant, extraction time and aqueous media (HNO3, NH4OH). Among these extractants, the Cynaex-923 is efficient and promising for rapid separation and production of NCA 199Au from HNO3 by high extraction %. Selective extraction of 199Au from other Pt and Ir radioisotopes is observed. High recovery of 199Au was obtained in the case of Cyanex-923 using 0.05 M thiourea dissolved in HCl or 2 M NaOH. Our results find the Cyanex-923 as a promising extractant for efficient separation of 199Au from irradiated Pt target with high yield (99%).

Highly Stable Silver(I) Complexes with Cyclen-Based Ligands Bearing Sulfide Arms: A Step Toward Silver-111 Labeled Radiopharmaceuticals

With a half-life of 7.45 days, silver-111 (β_max 1.04 MeV, E_γ 245.4 keV [I_γ 1.24%], E_γ 342.1 keV [I_γ 6.7%]) is a promising candidate for targeted cancer therapy with β^- emitters as well as for associated SPECT imaging. For its clinical use, the development of suitable ligands that form sufficiently stable Ag⁺-complexes in vivo is required. In this work, the following sulfur-containing derivatives of tetraazacyclododecane (cyclen) have been considered as potential chelators for silver-111: 1,4,7,10-tetrakis(2-(methylsulfanyl)ethyl)-1,4,7,10-tetraazacyclododecane (DO4S), (2S,5S,8S,11S)-2,5,8,11-tetramethyl-1,4,7,10-tetrakis(2-(methylsulfanyl)ethyl)-1,4,7,10-tetraazacyclododecane (DO4S4Me), 1,4,7-tris(2-(methylsulfanyl)ethyl)-1,4,7,10-tetraazacyclododecane (DO3S), 1,4,7-tris(2-(methylsulfanyl)ethyl)-10-acetamido-1,4,7,10-tetraazacyclododecane (DO3SAm), and 1,7-bis(2-(methylsulfanyl)ethyl)-4,10,diacetic acid-1,4,7,10-tetraazacyclododecane (DO2A2S). Natural Ag⁺ was used in pH/Ag-potentiometric and UV-vis spectrophotometric studies to determine the metal speciation existing in aqueous NaNO₃ 0.15 M at 25 °C and the equilibrium constants of the complexes, whereas NMR and DFT calculations gave structural insights. Overall results indicated that sulfide pendant arms coordinate Ag⁺ allowing the formation of very stable complexes, both at acidic and physiological pH. Furthermore, radiolabeling, stability in saline phosphate buffer, and metal-competition experiments using the two ligands forming the strongest complexes, DO4S and DO4S4Me, were carried out with [¹¹¹Ag]Ag⁺ and promising results were obtained.

Zinc and copper complexes with azacrown ethers and their comparative stability in vitro and in vivo

Copper-based radiopharmaceuticals are of high interest these days owing to the decay properties of copper radioisotopes. In contrast, labeled zinc compounds have been less studied for applications in nuclear medicine. In this study, the stability of labeled zinc and copper complexes with two azacrown ether ligands was investigated and compared. Then, the in vitro and in vivo stability of the studied zinc complexes was demonstrated, with the complexes showing promise for biomedical applications. In contrast, analogous copper complexes quickly dissociated in the presence of serum proteins. Furthermore, a simple method for the production of radiochemically pure 65Zn was proposed, and the opportunity for its use as a surrogate radionuclide for research into potential zinc-containing radiopharmaceuticals was demonstrated.

Mass Spectrometry Reveals Complexing Properties of Modified PNP-Lariat Ether Containing Benzyl Derivative of (S)-Prolinamine

In the investigation presented here the synthesis of new lariat ether derivative obtained from the modification of tetrapyrrolidinyl-PNP-crown ether macrocycle is described. The polyheterotopic molecular coreceptor consisted of the replacement of chlorine atoms with an optically active (S)-(1-benzylpyrrolidin-2-yl) methanamine. The structure was confirmed by using elemental analysis, mass spectrometry, and NMR spectroscopy. This work covers results concerning the complexing properties of the new ligand towards Ag⁺, Cu^2+, Co^2+, Ni²⁺, and Zn²⁺ ions. The formation of non-covalent complexes of 1:1 stoichiometry with the Cu^2+, Co^2+, Ni²⁺, and Zn²⁺ ions have been confirmed by mass spectrometry. Due to the previous work and application possibilities, a large emphasis was put on the investigation of the complexation ability of lariat ether with silver (I) cation to determine stability constants by direct potentiometric method. In this case, the formation of four different forms of complexes AgL, Ag₂L, Ag₃L, and Ag₄L has been proved. The observed unusual binding through the nitrogen atoms from the exocyclic substituents may provide the structural unit to build a new coordination polymers.

Radiometals for imaging and theranostics, current production, and future perspectives

The aim of this review is to make the reader familiar with currently available radiometals, their production modes, capacities, and quality concerns related to their medical use, as well as new emerging radiometals and irradiation technologies from the perspective of their diagnostic and theranostic applications. Production methods of ¹⁷⁷ Lu serve as an example of various issues related to the production yield, specific activity, radionuclidic and chemical purity, and production economy. Other radiometals that are currently used or explored for potential medical applications, with particular focus on their theranostic value, are discussed. Using radiometals for diagnostic imaging and therapy is on the rise. The high demand for radiometals for medical use prompts investigations towards using alternative irradiation reactions, while using existing nuclear reactors and accelerator facilities. This review discusses these production capacities and what is necessary to cover the growing demand for theranostic nuclides.

Chromatographic separation of the theranostic radionuclide 111Ag from a proton irradiated thorium matrix

Column chromatographic methods have been developed to separate no-carrier-added ¹¹¹Ag from proton irradiated thorium targets and associated fission products as an ancillary process to an existing ²²⁵Ac separation design. Herein we report the separation of ¹¹¹Ag both prior and subsequent to ²²⁵Ac recovery using CL resin, a solvent impregnated resin (SIR) that carries an organic solution of alkyl phosphine sulfides (R₃P = S) and alkyl phosphine oxides (R₃P = O). The recovery yield of ¹¹¹Ag was 93 ± 9% with a radiochemical purity of 99.9% (prior) and 87 ± 9% with a radiochemical purity of 99.9% (subsequent to) ²²⁵Ac recovery. Both processes were successfully performed with insignificant impacts on ²²⁵Ac yields or quality. Measured equilibrium distribution coefficients for silver and ruthenium (a residual contaminant) on CL resin in hydrochloric and nitric acid media are reported, to the best of our knowledge, for the first time. Additionally, measured cross sections for the production of ¹¹¹Ag and ^110mAg for the ²³²Th(p,f)^110m,111Ag reactions are reported within.

Reactor production of no-carrier-added 199Au for biomedical applications

This investigation described development of a technology for the reactor production of no-carrier-added (NCA) ¹⁹⁹Au using natural Pt target followed by chemical separation of ¹⁹⁹Au employing liquid–liquid extraction (LLX) using ethyl acetate.

An electro-amalgamation approach to produce 175Yb suitable for radiopharmaceutical applications

175Yb is a prospective reactor produced radionuclide suitable for preparation of therapeutic radiopharmaceuticals. However, a major restraint in the use of 175Yb produced via the (n, γ) reaction, for therapeutic applications, is the presence of longer-lived 177Lu impurity which is co-produced along with 175Yb on irradiation of natural Yb2O3 target. A radiochemical separation procedure adopting electro-amalgamation approach for the removal of 177Lu impurity from 175Yb has been critically evaluated. The experimental parameters such as applied potential, electrolysis time and the pH of the electrolyte, affecting the electrochemical separation process, were studied and optimized. The developed radiochemical procedure was extensively tested for purification of up to 15 GBq of 175Yb. The purified 175Yb could be obtained in HCl medium with ∼95% yield. The 177Lu impurity could not be detected in the purified product and 175Yb was found suitable for the preparation of potential radiotherapeutic agents.

Preparation and preliminary biological evaluation of a 177Lu labeled nitroimidazole derivative for possible use in targeted tumor therapy

The preparation and preliminary biological evaluation of a metronidazole-BFCA (bifunctional chelating agent) conjugate labeled with 177Lu is reported. Metronidazole, a well known hypoxia marker has been suitably derivatized and coupled with a polyazamacrocyclic BFCA, namely, para-aminobenzyl-1,4,7,10-tetraazacyclododecane-1,4,7,10-tetraacetic acid (p-amino-benzyl-DOTA). 177Lu, which is presently being considered as one of the pivotal radionuclides for targeted therapy was produced in adequate specific activity (∼185 TBq/g) and high radionuclidic purity (99.99%) by irradiating enriched (60.6% 176Lu) Lu2O3 target at a moderate thermal neutron flux of 3×1013 n/cm2/s. The metronidazole-BFCA conjugate was radiolabeled with 177Lu in high radiochemical purity (97%). Preliminary biodistribution studies carried out in Swiss mice bearing fibrosarcoma tumors revealed good tumor uptake (1.30% ID/g at 30 min post-injection) with rapid renal clearance (94.48% ID at 30 min post-injection) and significant tumor to blood (28.00 at 3 h post-injection) and tumor to muscle (14.00 at 3 h post-injection) ratios.

Biological evaluation of 153Sm and 166Ho complexes with tetraazamacrocycles containing methylcarboxylate and/or methylphosphonate pendant arms

153Sm and 166Ho complexes with two series of tetraazamacrocyclic ligands containing methylcarboxylate and/or methylphosphonate pendant arms were synthesized and their charge, lipophilicity, protein binding and in vitro and in vivo behaviour evaluated. The first series has the same backbone, a 14-membered tetraazamacrocycle containing a pyridine unit with different pendant arms, namely methylcarboxylates (ac3py14) or methylphosphonates (MeP2py14 and P3py14). The second series comprises 12- to 14-membered tetraazamacrocycles having methylcarboxylates and/or methylphosphonates as pendant arms (trans-DO2A2P, TRITA, TRITP, TETA and TETP). The 153Sm/166Ho complexes with the 14-membered tetraazamacrocycles containing the pyridine unit are neutral, hydrophilic, have a significant plasmatic protein binding, are unstable in vivo and present a slow rate of radioactivity excretion and high hepatic retention. 153Sm/166Ho complexes with the 12- to 14-membered tetraazamacrocycles are quantitatively prepared, except those with TETP. These complexes are hydrophilic, have an overall negative charge and present a medium to low plasmatic protein binding.

The 153Sm/166Ho- trans-DO2A2P, 153Sm/166Ho-TRITA and 166Ho-TRITP complexes are stable in vitro and in vivo, presenting a rapid clearance from main organs and a high rate of whole body radioactivity excretion. Biological profile of 153Sm/166Ho-TRITA complexes makes them promising candidates for therapy when conjugated to a biomolecule, while 166Ho-TRITP is potentially useful for bone targeting due to its considerable uptake by bone.

Cross sections for production of the therapeutic radioisotopes 198Au and 199Au in proton and deuteron induced reactions on 198Pt

The possible production of the therapeutic radioisotopes 198Au and 199Au using charged particle reactions at cyclotrons was investigated. For the first time, excitation functions for the 198Pt(p,n)198gAu, 198Pt(d,2n)198m,gAu and 198Pt(d,x) 199Au nuclear reactions were measured up to 40 MeV proton and 20 MeV deuteron energies. The results were compared with calculations performed with the computer code ALICE-IPPE. Acceptable overall agreement was obtained. Production and product quality parameters are discussed on the basis of the measured cross sections and from the deduced integral yields.

Production of medical radioactive isotopes using KIPT electron driven subcritical facility

Kharkov Institute of Physics and Technology (KIPT) of Ukraine in collaboration with Argonne National Laboratory (ANL) has a plan to construct an electron accelerator driven subcritical assembly. One of the facility objectives is the production of medical radioactive isotopes. This paper presents the ANL collaborative work performed for characterizing the facility performance for producing medical radioactive isotopes. First, a preliminary assessment was performed without including the self-shielding effect of the irradiated samples. Then, more detailed investigation was carried out including the self-shielding effect, which defined the sample size and location for producing each medical isotope. In the first part, the reaction rates were calculated as the multiplication of the cross section with the unperturbed neutron flux of the facility. Over fifty isotopes have been considered and all transmutation channels are used including (n, gamma), (n, 2n), (n, p), and (gamma, n). In the second part, the parent isotopes with high reaction rate were explicitly modeled in the calculations. Four irradiation locations were considered in the analyses to study the medical isotope production rate. The results show the self-shielding effect not only reduces the specific activity but it also changes the irradiation location that maximizes the specific activity. The axial and radial distributions of the parent capture rates have been examined to define the irradiation sample size of each parent isotope.

A versatile technique for radiochemical separation of medically useful no-carrier-added (nca) radioarsenic from irradiated germanium oxide targets

A method for the separation of no-carrier-added (nca) arsenic radionuclides from bulk amounts of irradiated germanium oxide (GeO2) target was developed in view of their potentialities in different biological and nuclear medicine applications. The beta- emitting 77As radionuclide, produced by the decay of 77Ge through the natGe(n,gamma)77Ge nuclear reaction, was used for standardization of the radiochemical separation procedure. The radiochemical separation was performed by precipitation followed by solvent extraction. About 99% post-irradiation recovery of the GeO2 target material, in a form suitable for reuse in future irradiation, was achieved. The developed method was suitable for the production of nca arsenic radionuclides either as trivalent or pentavalent arsenic in various vehicles which provided flexibility of formulations of different kinds of compound. The overall radiochemical yield for the complete separation of 77As was 90%. The separated nca 77As was of high radionuclidic purity and did not contain detectable amounts of the target material. This method can be adopted for the radiochemical separation of other different arsenic radionuclides produced from GeO2 through cyclotron as well as reactor irradiation.

On the preparation of a therapeutic dose of 177Lu-labeled DOTA–TATE using indigenously produced 177Lu in medium flux reactor

177Lu could be produced with a specific activity of approximately 23,000 mCi/mg (850GBq/mg) by neutron activation using enriched 176Lu (64.3%) target when irradiation was carried out at a thermal neutron flux of 1 x 10(14) n/cm(2)/s for 21 d. 177Lu-DOTA-TATE could be prepared in high radiochemical yield (approximately 99%) and adequate stability using the 177Lu produced indigenously. The average level of radionuclidic impurity burden in 177Lu due to 177mLu was found to be 250 nCi of 177mLu/1 mCi of 177Lu (9.25 kBq/37 MBq) at the end of bombardment, which corresponds to 0.025% of the total activity produced. The maximum specific activity achievable via careful optimization of the irradiation parameters was found to be adequate for the preparation of a therapeutic dose of the radiopharmaceutical. The in-house preparation of this agent using 25 microg (17.41 nmole) of DOTA-TATE and indigenously produced 177Lu (0.8 microg, 4.52 nmole), corresponding to peptide/Lu ratio of 3.85 yielded 98.7% complexation. Allowing possibility of decay due to transportation to users, it has been possible to demonstrate that at our end, a single patient dose of 150-200 mCi (5.55-7.40 GBq) can be prepared by using 250-333 microg of DOTA-TATE conjugate. This amount compares well with 177Lu-DOTA-TATE prepared for a typical peptide receptor radionuclide therapy (PRRT) procedure which makes use of 100 microg of the DOTA-TATE conjugate, which incorporates 50 mCi (1.85 GBq) of 177Lu activity, thereby implying that in order to achieve a single patient dose of 150-200 mCi (5.55-7.40 GBq), 300-400 microg of the conjugate needs to be used.

Preparation and preliminary biological evaluation of 177Lu-labelled hydroxyapatite as a promising agent for radiation synovectomy of small joints

AIM

Lutetium-(177)Lu) is considered to be a promising radionuclide for use in radiation synovectomy of small-sized joints owing to its favourable decay characteristics [t(1/2)=6.73 days, E(beta)(max)=0.49 MeV, E(gamma)=113 keV (6.4%), 208 keV (11%)] and feasible and cost-effective production route. Hydroxyapatite particles are regarded as one of the most suitable carriers for applications in radiation synovectomy, and labelling with (177)Lu has been envisaged. The present work describes the preparation and preliminary biological evaluation of (177)Lu-labelled hydroxyapatite particles.

METHODS

(177)Lu-labelled hydroxyapatite particles were prepared using (177)Lu produced by thermal neutron irradiation of a natural (2.6% (177)Lu) Lu(2)O(3) target and hydroxyapatite particles (particle size, 2-10 microm) prepared in-house. The biological efficacy of the radiolabelled preparation was tested by recording serial gamma scintigraphic images after injecting the agent in both normal and arthritic knee joints of Wistar rats.

RESULTS

(177)Lu-hydroxyapatite was prepared with high yield and high radiochemical purity (approximately 99%) and the radiolabelled particles showed excellent in-vitro stability at room temperature. Serial scintigraphic images of normal and arthritic Wistar rats showed complete retention of activity within the synovial cavity, with no measurable activity leaching out from the joint until 168 h post-injection.

CONCLUSION

Studies with (177)Lu-hydroxyapatite indicate its potential for use as an agent for radiation synovectomy of digital joints, as a viable alternative to (169)Er-based agents. The results also demonstrate the possibility of preparing a large number of patient doses of (177)Lu-hydroxyapatite from indigenously produced (177)Lu using a natural target.

An estradiol-conjugate for radiolabelling with 177Lu: an attempt to prepare a radiotherapeutic agent

177Lu is presently being considered as one of the most promising radionuclide for targeted therapy owing to its suitable decay characteristics. 177Lu in high radionuclidic purity (99.99%) and moderate specific activity (100-110 TBq/g) was produced using enriched (60.6% 176Lu) Lu2O3 target. The macrocycle 1,4,7,10-tetraazacyclododecane-1,4,7,10-tetraacetic acid (DOTA) is known to form stable complexes with lanthanides. Herein, we describe a novel attempt to introduce 177Lu in the estradiol moiety through a steroidal-BFCA (Bifunctional Chelating Agent) conjugate. The preparation of a steroid conjugate via coupling of 6alpha-amino-17beta-estradiol with a C-functionalized DOTA derivative viz. p-NCS-benzyl-DOTA as a BFCA and thereafter the radiolabelling of the conjugate with 177Lu is reported. Biological activity of the resultant estradiol-DOTA conjugate after radiolabelling was studied by carrying out preliminary in vitro cell uptake studies with MCF-7, human breast carcinoma cell line expressing estrogen receptors as well as binding studies with anti-estradiol antibodies.

Radiopharmaceuticals for targeted radiotherapy

This work intends to find specific radiopharmaceuticals for cancer therapy based on beta (153Sm and 166Ho) or Auger (99Tc(m)) emitter radionuclides, using cyclic and acyclic polyamines as bifunctional chelators. These chelators are designed to allow the binding of a tumour seeking biomolecule and/or a DNA intercalator. The cyclic amines, such as 1,4,7,10-tetraazacyclododecane-1,4,7,10-tetraacetic acid, 1,4,8,11-tetraazacyclotetradecane-1,4,8,11-tetraacetic acid and 1,4,7,10-tetraazacyclotridecane-1,4,7,10-tetraacetic acid, were radiolabelled with 153Sm and 166Ho. The radiochemical and biological behaviour of the resulting complexes were evaluated in order to assess their potential as building blocks for the attachment of selected biomolecules, with the aim of further applying them for the development of specific therapeutic radiopharmaceuticals. Novel pyrazolyldiamines, bearing a DNA intercalating anthracenyl fragment, were also explored to synthesize radioactive complexes with the fac-[99Tc(m)(CO)]3]+ moiety. The identity of these 99Tc(m) tricarbonyl complexes was confirmed by high-performance liquid chromatography comparison with rhenium congeners fully characterized. By including a DNA intercalator into the chelator framework, we expect to induce more efficient and selective damage to the DNA of cancer cells by the action of the short-range Auger electrons emitted by 99Tc(m).

Preparation and preliminary biological evaluation of a 177Lu labeled sanazole derivative for possible use in targeting tumor hypoxia

The preparation of a polyazamacrocyclic-nitrotriazole conjugate for radiolabeling with the therapeutic radioisotope viz. (177)Lu is described. The nitroimidazole used for the present study is [N-2'(carboxyethyl)-2-(3'-nitro-1'-triazolyl)acetamide], the carboxylic acid derivative of sanazole, which possesses an optimal combination of desired properties such as, selective toxicity for hypoxic cells, lowered lipophilicity resulting in lowered neurotoxicity. The bifunctional chelating agent is a DOTA derivative viz. 1,4,7,10-tetraaza-1-(4'-aminobenzylacetamido)-cyclododecane-4,7,10- triacetic acid (p-amino-DOTA-anilide). (177)Lu was produced in adequate specific activity (110TBq/g) and high radionuclidic purity (approximately 100%) by irradiating enriched (60.6% (176)Lu) Lu(2)O(3) target and used for radiolabeling of the sanazole-BFCA conjugate. approximately 98% Complexation yield was achieved under optimized conditions. The complex has been characterized by paper chromatography and HPLC studies. Bioevaluation studies in Swiss mice bearing fibrosarcoma tumors revealed moderate tumor uptake (0.88%/g at 1h post-injection) with favorable tumor to blood (4.00 at 1h post-injection) and tumor to muscle (4.63 at 1h post-injection) ratios.

Molecular imaging with copper-64

Molecular imaging is expected to change the face of drug discovery and development. The ability to link imaging to biology for guiding therapy should improve the rate at which novel imaging technologies, probes, contrast agents, drugs and drug delivery systems can be transferred into clinical practice. Nuclear medicine imaging, in particular, positron emission tomography (PET) allows the detection and monitoring of a variety of biological and pathophysiological processes, at tracer quantities of the radiolabelled target agents, and at doses free from pharmacological effects. In the field of drug discovery and development, the use of radiotracers for radiolabelling target agents has now become one of the essential tools in identifying, screening and development of new target agents. In this regard, (64)Cu (t(1/2)=12.7 h) has been identified as an emerging PET isotope. Its half-life is sufficiently long for radiolabelling a range of target agents and its ease of production and adaptable chemistry make it an excellent radioisotope for use in molecular imaging. This review describes recent advances, in the routes of (64)Cu production, design and application of bi-functional ligands for use in radiolabelling with (64/67)Cu(2+), and their significance and anticipated impact on the field of molecular imaging and drug development.

153Sm and 166Ho complexes with tetraaza macrocycles containing pyridine and methylcarboxylate or methylphosphonate pendant arms

A set of tetraaza macrocycles containing pyridine and methylcarboxylate (ac(3)py14) or methylphosphonate (MeP(2)py14 and P(3)py14) pendant arms were prepared and their stability constants with La(3+), Sm(3+), Gd(3+) and Ho(3+) determined by potentiometry at 25 degrees C and 0.10 M ionic strength in NMe(4)NO(3). The metal:ligand ratio for (153)Sm and (166)Ho and for ac(3)py14, MeP(2)py14 and P(3)py14, as well as the pH of the reaction mixtures, were optimized to achieve a chelation efficiency higher than 98%. These radiocomplexes are hydrophilic and have a significant plasmatic protein binding. In vitro stability was studied in physiological solutions and in human serum. All complexes are stable in saline and PBS, but 20% of radiochemical impurities were detected after 24 h of incubation in serum. Biodistribution studies in mice indicated a slow rate of clearance from blood and muscle, a high and rapid liver uptake and a very slow rate of total radioactivity excretion. Some bone uptake was observed for complexes with MeP(2)py14 and P(3)py14, which was enhanced with time and the number of methylphosphonate groups. This biological profile supports the in vitro instability found in serum and is consistent with the thermodynamic stability constants found for these complexes.

Production logistics of 177Lu for radionuclide therapy

Owing to its favourable decay characteristics 177Lu [T(1/2)=6.71 d, Ebeta(max)=497 keV] is an attractive radionuclide for various therapeutic applications. Production of 177Lu using [176Lu (n,gamma)177Lu] reaction by thermal neutron bombardment on natural as well as enriched lutetium oxide target is described. In all, approximately 4 TBq/g (108 Ci/g) of 177Lu was obtained using natural Lu target after 7 d irradiation at 3 x 10(13) n/cm2/s thermal neutron flux while it was approximately 110 TBq/g (3000 Ci/g) of 177Lu when 60.6% enriched 176Lu target was used. In both the cases, radionuclidic purity was approximately 100%, only insignificant quantity of 177mLu [T(1/2)=160.5 d, Ebeta(max)=200 keV] could be detected as the radionuclidic impurity. Production logistics using different routes of production is compared. Possible therapeutic applications of 177Lu are discussed and its merits highlighted by comparison with other therapeutic radionuclides.