N. Michel

Optimization of reaction conditions for the radiolabeling of DOTA and DOTA-peptide with 44m/44Sc and experimental evidence of the feasibility of an in vivo PET generator

INTRODUCTION Among the number of generator systems providing radionuclides with decay parameters promising for imaging and treatment applications, there is the (44)Ti (T1/2=60 years)/(44)Sc (T1/2=3.97 h) generator. This generator provides a longer-lived daughter for extended PET/CT measurements compared to the chemically similar system (68)Ge/(68)Ga. Scandium also exists as (47)Sc, a potential therapeutic radionuclide. It is possible to produce (44)Sc in a cyclotron using, for example, the (44)Ca (d, n) (44)Sc nuclear reaction. In that case, the isomeric state (44 m)Sc (T1/2=58.6h) is co-produced and may be used as an in vivo(44 m)Sc/(44)Sc generator. The aim of this study is to evaluate the feasibility of this in vivo(44 m)Sc/(44)Sc generator and to demonstrate that the daughter radionuclide stays inside the chelator after decay of the parent radionuclide. Indeed, the physico-chemical process occurring after the primary radioactive decay (EC, IT, Auger electron …) has prevented in many cases the use of in-vivo generator, because of the post-effect as described in the literature. METHODS The DOTA macrocyclic ligand forms stable complexes with many cations and has been shown to be the most suitable chelating moiety for scandium. Initially, the radiolabeling of DOTA and a DOTA-peptide (DOTATATE) with Sc was performed and optimized as a function of time, pH, metal-to-ligand ratio and temperature. Next, the physico-chemical processes that could occur after the decay (post-effect) were studied. (44 m)Sc(III)-labeled DOTA-peptide was quantitatively adsorbed on a solid phase matrix through a hydrophobic interaction. Elutions were then performed at regular time intervals using a DTPA solution at various concentrations. Finally, the radiolabelled complex stability was studied in serum. RESULTS Radiolabeling yields ranged from 90% to 99% for metal-to-ligand ratio ranging from 1:10 to 1:500 for DOTA or DOTATATE respectively. The optimum physico-chemical parameters were pH=4-6, t=20 min, T=70°C. Then, the (44 m)Sc-DOTATATE complex, radiolabeled at 98%, was adsorbed through a hydrophobic interaction to a solid phase. Unlabeled scandium was completely eluted from the column whereas the Sc-DOTATATE complex was 100% retained. The release of (44)Sc from the complex due to decay was less than 1% over 2 periods of (44 m)Sc, independent of the DTPA concentration used for elution. (44 m)Sc/(44)Sc-DOTATATE was stable in serum over 72 h. CONCLUSIONS The results indicate that the decay of (44 m)Sc to (44)Sc does not affect the integrity of the radiolabeled compound. Thus the (44 m)Sc/(44)Sc generator is chemically valid and stable in serum. It could be used for PET imaging as an in-vivo generator increasing the life time of the scandium and allowing the use of antibody as labelled compound. Further in-vivo biological evaluations should complete this work.

Cyclotron production of high purity 44m,44Sc with deuterons from 44CaCO3 targets

INTRODUCTION Due to its longer half-life, (44)Sc (T1/2 = 3.97 h) as a positron emitter can be an interesting alternative to (68)Ga (T1/2 = 67.71 min). It has been already proposed as a PET radionuclide for scouting bone disease and is already available as a (44)Ti/(44)Sc generator. (44)Sc has an isomeric state, (44 m)Sc (T1/2 = 58.6 h), which can be co-produced with (44)Sc and that has been proved to be considered as an in-vivo PET generator (44 m)Sc/(44)Sc. This work presents the production route of (44 m)Sc/(44)Sc generator from (44)Ca(d,2n), its extraction/purification process and the evaluation of its performances. METHODS Irradiation was performed in a low activity target station using a deuteron beam of 16 MeV, which favors the number of (44 m)Sc atoms produced simultaneously to (44)Sc. Typical irradiation conditions were 60 min at 0.2 μA producing 44 MBq of (44)Sc with a (44)Sc/(44 m)Sc activity ratio of 50 at end of irradiation. Separations of the radionuclides were performed by means of cation exchange chromatography using a DGA® resin (Triskem). Then, the developed process was applied with bigger targets, and could be used for preclinical studies. RESULTS The extraction/purification process leads to a radionucleidic purity higher than 99.99% ((43)Sc, (46)Sc, (48)Sc < DL). (44 m)Sc/(44)Sc labeling towards DOTA moiety was performed in order to get an evaluation of the specific activities that could be reached with regard to all metallic impurities from the resulting source. Reaction parameters of radiolabeling were optimized, reaching yields over 95%, and leading to a specific activity of about 10-20 MBq/nmol for DOTA. A recycling process for the enriched (44)Ca target was developed and optimized. CONCLUSION The quality of the final batch with regard to radionucleidic purity, specific activity and metal impurities allowed a right away use for further radiopharmaceutical evaluation. This radionucleidic pair of (44 m)Sc/(44)Sc offers a quite interesting PET radionuclide for being further evaluated as an in-vivo generator.

Production of scandium-44 m and scandium-44 g with deuterons on calcium-44: cross section measurements and production yield calculations.

HIGHLIGHTS • Production of Sc-44 m, Sc-44 g and contaminants. • Experimental values determined using the stacked-foil technique. • Thick-Target production Yield (TTY) calculations. • Comparison with the TALYS code version 1.6.Among the large number of radionuclides of medical interest, Sc-44 is promising for PET imaging. Either the ground-state Sc-44 g or the metastable-state Sc-44 m can be used for such applications, depending on the molecule used as vector. This study compares the production rates of both Sc-44 states, when protons or deuterons are used as projectiles on an enriched Calcium-44 target. This work presents the first set of data for the deuteron route. The results are compared with the TALYS code. The Thick-Target production Yields of Sc-44 m and Sc-44 g are calculated and compared with those for the proton route for three different scenarios: the production of Sc-44 g for conventional PET imaging, its production for the new 3 γ imaging technique developed at the SUBATECH laboratory and the production of a Sc-44 m/Sc-44 g in vivo generator for antibody labelling.

Cross section measurements of deuteron induced nuclear reactions on natural tungsten up to 34 MeV.

(186g)Re is a β-/γ emitter of great interest for nuclear medicine. It has shown successful results on bone metastases palliation and has similar chemical properties as (99m)Tc, the most commonly used imaging agent. (186g)Re is routinely produced using rhenium target in nuclear reactor. Higher specific activity could be obtained using accelerators. In this paper, production cross section values are presented for the (nat)W(d,x)(186g)Re reaction up to 34MeV, using the stacked-foils method and gamma spectrometry. From this data set, the thick target production yield of (186g)Re is determined and compared with the validated values of the IAEA and also with the proton route. The production cross sections of the (nat)W(d,x)(183,182g,184m,184g,181)Re and (nat)W(d,x)(187)W reactions have also been determined. A good agreement is found with the literature. Our data are compared with the version 1.6 (December 2013) of the TALYS code which shows discrepancies both on the shape and on the amplitude for these deuteron induced reactions.

How to produce high specific activity tin-117 m using alpha particle beam

Tin-117m is an interesting radionuclide for both diagnosis and therapy, thanks to the gamma-ray and electron emissions, respectively, resulting from its decay to tin-117g. The high specific activity of tin-117m is required in many medical applications, and it can be obtained using a high energy alpha particle beam and a cadmium target. The experiments performed at the ARRONAX cyclotron (Nantes, France) using an alpha particle beam delivered at 67.4MeV provide a measurement of the excitation function of the Cd-nat(α,x)Sn-117m reaction and the produced contaminants. The Cd-116(α,3n)Sn-117m production cross section has been deduced from these experimental results using natural cadmium. Both production yield and specific activity as a function of the projectile energy have been calculated. These informations help to optimize the irradiation conditions to produce tin-117m with the required specific activity using α particles with a cadmium target.

232Th(d,4n)230Pa cross-section measurements at ARRONAX facility for the production of 230U

INTRODUCTION (226)Th (T1/2=31 min) is a promising therapeutic radionuclide since results, published in 2009, showed that it induces leukemia cells death and activates apoptosis pathways with higher efficiencies than (213)Bi. (226)Th can be obtained via the (230)U α decay. This study focuses on the (230)U production using the (232)Th(d,4n)(230)Pa(β-)(230)U reaction. METHODS Experimental cross sections for deuteron-induced reactions on (232)Th were measured from 30 down to 19 MeV using the stacked-foil technique with beams provided by the ARRONAX cyclotron. After irradiation, all foils (targets as well as monitors) were measured using a high-purity germanium detector. RESULTS Our new (230)Pa cross-section values, as well as those of (232)Pa and (233)Pa contaminants created during the irradiation, were compared with previous measurements and with results given by the TALYS code. Experimentally, same trends were observed with slight differences in orders of magnitude mainly due to the nuclear data change. Improvements are ongoing about the TALYS code to better reproduce the data for deuteron-induced reactions on (232)Th. CONCLUSIONS Using our cross-section data points from the (232)Th(d,4n)(230)Pa reaction, we have calculated the thick-target yield of (230)U, in Bq/μA·h. This value allows now to a full comparison between the different production routes, showing that the proton routes must be preferred.

Deuteron induced Tb-155 production, a theranostic isotope for SPECT imaging and auger therapy.

Several terbium isotopes are suited for diagnosis or therapy in nuclear medicine. Tb-155 is of interest for SPECT imaging and/or Auger therapy. High radionuclide purity is mandatory for many applications in medicine. The quantification of the activity of the produced contaminants is therefore as important as that of the radionuclide of interest. The experiments performed at the ARRONAX cyclotron (Nantes, France), using the deuteron beam delivered up to 34MeV, provide an additional measurement of the excitation function of the Gd-nat(d,x)Tb-155 reaction and of the produced terbium and gadolinium contaminants. In this study, we investigate the achievable yield for each radionuclide produced in natural gadolinium as a function of the deuteron energy. Other reactions are discussed in order to define the production route that could provide Tb-155 with a high yield and a high radionuclide purity. This article aims to improve data for the Gd-nat(d,x) reaction and to optimize the irradiation conditions required to produce Tb-155.