Proton-induced production and radiochemical isolation of 44Ti from scandium metal targets for 44Ti/44Sc generator development.

Scandium-44g (half-life 3.97h) shows promise for application in positron emission tomography (PET), due to favorable decay parameters. One of the sources of 44gSc is the 44Ti/44gSc generator, which can conveniently provide this radioisotope on a daily basis at a diagnostic facility. Titanium-44 (half-life 60.0 a), in turn, can be obtained via proton irradiation of scandium metal targets. A substantial 44Ti product batch, however, requires high beam currents, long irradiation times and an elaborate chemical procedure for 44Ti isolation and purification. This study describes the production of a combined 175MBq (4.7mCi) batch yield of 44Ti in week long proton irradiations at the Los Alamos Isotope Production Facility (LANL-IPF) and the Brookhaven Linac Isotope Producer (BNL-BLIP). A two-step ion exchange chromatography based chemical separation method is introduced: first, a coarse separation of 44Ti via anion exchange sorption in concentrated HCl results in a 44Tc/Sc separation factor of 102-103. A second, cation exchange based step in HCl media is then applied for 44Ti fine purification from residual Sc mass. In summary, this method yields a 90-97% 44Ti recovery with an overall Ti/Sc separation factor of ≥106.

Bulk production and evaluation of high specific activity 186gRe for cancer therapy using enriched 186WO3 targets in a proton beam.

INTRODUCTION: Rhenium-186g (t1/2 = 3.72 d) is a ß- emitting isotope suitable for theranostic applications. Current production methods rely on reactor production by way of the reaction 185Re(n,γ)186gRe, which results in low specific activities limiting its use for cancer therapy. Production via charged particle activation of enriched 186W results in a 186gRe product with a higher specific activity, allowing it to be used more broadly for targeted radiotherapy applications. This targets the unmet clinical need for more efficient radiotherapeutics. METHODS: A target consisting of highly enriched, pressed 186WO3 was irradiated with protons at the Los Alamos National Laboratory Isotope Production Facility (LANL-IPF) to evaluate 186gRe product yield and quality. LANL-IPF was operated in a dedicated nominal 40 MeV mode. Alkaline dissolution followed by anion exchange chromatography was used to isolate 186gRe from the target material. Phantom and radiolabeling studies were conducted with the produced 186gRe activity. RESULTS: A 186gRe batch yield of 1.38 ± 0.09 MBq/µAh or 384.9 ± 27.3 MBq/C was obtained after 16.5 h in a 205 µA average/230µA maximum current proton beam. The chemical recovery yield was 93% and radiolabeling was achieved with efficiencies ranging from 60-80%. True specific activity of 186gRe at EOB was determined via ICP-AES and amounted to 0.788 ± 0.089 GBq/µg (0.146 ± 0.017 GBq/nmol), which is approximately seven times higher than the product obtained from neutron capture in a reactor. Phantom studies show similar imaging quality to the gold standard 99mTc. CONCLUSIONS: We report a preliminary study of the large-scale production and novel anion exchange based chemical recovery of high specific activity 186gRe from enriched 186WO3 targets in a high-intensity proton beam with exceptional chemical recovery and radiochemical purity.

Crystal structure of the Mycobacterium tuberculosis dUTPase: insights into the catalytic mechanism.

The structure of Mycobacterium tuberculosis dUTP nucleotidohydrolase (dUTPase) has been determined at 1.3 Angstrom resolution in complex with magnesium ion and the non-hydrolyzable substrate analog, alpha,beta-imido dUTP. dUTPase is an enzyme essential for depleting potentially toxic concentrations of dUTP in the cell. Given the importance of its biological role, it has been proposed that inhibiting M.tuberculosis dUTPase might be an effective means to treat tuberculosis infection in humans. The crystal structure presented here offers some insight into the potential for designing a specific inhibitor of the M.tuberculosis dUTPase enzyme. The structure also offers new insights into the mechanism of dUTP hydrolysis by providing an accurate representation of the enzyme-substrate complex in which both the metal ion and dUTP analog are included. The structure suggests that inclusion of a magnesium ion is important for stabilizing the position of the alpha-phosphorus for an in-line nucleophilic attack. In the absence of magnesium, the alpha-phosphate of dUTP can have either of the two positions which differ by 4.5 Angstrom. A transiently ordered C-terminal loop further assists catalysis by shielding the general base, Asp83, from solvent thus elevating its pK(a) so that it might in turn activate a tightly bound water molecule for nucleophilic attack. The metal ion coordinates alpha, beta, and gamma phosphate groups with tridentate geometry identical with that observed in the crystal structure of DNA polymerase beta complexed with magnesium and dNTP analog, revealing some common features in catalytic mechanism.