Development and biodistribution studies of 77As-labeled trithiol RM2 bioconjugates for prostate cancer: Comparison of [77As]As-trithiol-Ser-Ser-RM2 vs. [77As]As-trithiol-Glu-Ser-RM2.

INTRODUCTION: Recent progress with the production of 72As (2.49 Mev ß+max (64%), 3.33 Mev ß+max (16%), 834 keV γ (81%), t1/2: 26 h) and 77As (0.683 Mev ß-max (97%), 239 keV γ (1.59%), t1/2: 38.8 h) has facilitated their evaluation as a potential "theranostic pair" for PET imaging and radiotherapy. Our 3rd generation trithiol chelate with two carboxylic acid groups was further developed as a bifunctional chelate for radioarsenic. METHODS: The As complex with the trithiol chelate was synthesized and characterized. No carrier added (nca) [77As][H2AsO4-] was used for radiolabeling studies. The trithiol chelate was conjugated to the RM2 peptide (DPhe-Gln-Trp-Ala-Val-Gly-His-Sta-Leu-NH2) via solid phase peptide synthesis with two different linkers, Ser-Ser and Glu-Ser. The trithiol chelate and its RM2 bioconjugates were radiolabeled with nca 77As, and the RM2 bioconjugates were compared in initial biodistribution studies. RESULTS: The As diacid trithiol complex was characterized by 1H NMR, 13C NMR and HR-ESI-MS. The trithiol-RM2 precursor and As trithiol bioconjugates were characterized by HR-ESI-MS and/or LC-ESI-MS. Radiolabeling of the RM2 bioconjugates with 77As resulted in over 85% radiochemical yield for [77As]As-trithiol-Ser-Ser-RM2 ([77As]8) and 90% for [77As]As-trithiol-Glu-Ser-RM2 ([77As]9). Both radiotracers demonstrated excellent in vitro stability (≥ 90% remaining intact through 24 h in PBS buffer) and were more hydrophilic than previous analogues based on log D7.4 values. Biodistribution results of the two radiotracers in healthy CF-1 male mice demonstrated blockable pancreatic uptake at 1 h (82% for ([77As]8 and 78% for [77As]9) indicating specific gastrin-releasing peptide receptor (GRPR) uptake. The primary route of excretion was through the gastrointestinal system for both radiotracers. CONCLUSIONS: A new trithiol chelate with improved hydrophilicity was successfully conjugated to the RM2 peptide via two linkers, and high radiolabeling yield with nca 77As was achieved. In vivo biodistribution studies with both radiotracers demonstrated blockable pancreatic uptake suggestive of specific receptor uptake.

The application of poorly crystalline silicotitanate in production of 225Ac.

Actinium-225 (225Ac) can be produced from a Thorium-229/Radium-225 (229Th/225Ra) generator, from high/low energy proton irradiated natural Thorium or Radium-226 target. Titanium based ion exchanger were evaluated for purification of 225Ac. Poorly crystalline silicotitanate (PCST) ion exchanger had high selectivity for Ba, Ag and Th. 225Ac was received with trace amounts of 227Ac, 227Th and 223Ra, and the solution was used to evaluate the retention of the isotopes on PCST ion exchanger. Over 90% of the 225Ac was recovered from PCST, and the radiopurity was >99% (calculated based on 225Ac, 227Th, and 223Ra). The capacity of the PCST inorganic ion exchange for Barium and 232Th was determined to be 24.19 mg/mL for Barium and 5.05 mg/mL for Thorium. PCST ion exchanger could separate 225Ac from isotopes of Ra and Th, and the process represents an interesting one step separation that could be used in an 225Ac generator from 225Ra and/or 229Th. Capacity studies indicated PCST could be used to separate 225Ac produced on small 226Ra targets (0.3-1 g), but PCST did not have a high enough capacity for production scale Th targets (50-100 g).

Optimization of Cation Exchange for the Separation of Actinium-225 from Radioactive Thorium, Radium-223 and Other Metals.

Actinium-225 (225Ac) can be produced with a linear accelerator by proton irradiation of a thorium (Th) target, but the Th also underdoes fission and produces 400 other radioisotopes. No research exists on optimization of the cation step for the purification. The research herein examines the optimization of the cation exchange step for the purification of 225Ac. The following variables were tested: pH of load solution (1.5-4.6); rinse steps with various concentrations of HCl, HNO3, H2SO4, and combinations of HCl and HNO3; various thorium chelators to block retention; MP50 and AG50 resins; and retention of 20-45 elements with different rinse sequences. The research indicated that HCl removes more isotopes earlier than HNO3, but that some elements, such as barium and radium, could be eluted with ≥2.5 M HNO3. The optimal pH of the load solution was 1.5-2.0, and the optimized rinse sequence was five bed volumes (BV) of 1 M citric acid pH 2.0, 3 BV of water, 3 BV of 2 M HNO3, 6 BV of 2.5 M HNO3 and 20 BV of 6 M HNO3. The sequence recovered >90% of 225Ac with minimal 223Ra and thorium present.

Defining Processing Times for Accelerator Produced 225Ac and Other Isotopes from Proton Irradiated Thorium.

During the purification of radioisotopes, decay periods or time dependent purification steps may be required to achieve a certain level of radiopurity in the final product. Actinum-225 (Ac-225), Silver-111 (Ag-111), Astatine-211 (At-211), Ruthenium-105 (Ru-105), and Rhodium-105 (Rh-105) are produced in a high energy proton irradiated thorium target. Experimentally measured cross sections, along with MCNP6-generated cross sections, were used to determine the quantities of Ac-225, Ag-111, At-211, Ru-105, Rh-105, and other co-produced radioactive impurities produced in a proton irradiated thorium target at Brookhaven Linac Isotope Producer (BLIP). Ac-225 and Ag-111 can be produced with high radiopurity by the proton irradiation of a thorium target at BLIP.

Radiometric evaluation of diglycolamide resins for the chromatographic separation of actinium from fission product lanthanides.

Actinium-225 is a potential Targeted Alpha Therapy (TAT) isotope. It can be generated with high energy (≥ 100MeV) proton irradiation of thorium targets. The main challenge in the chemical recovery of 225Ac lies in the separation from thorium and many fission by-products most importantly radiolanthanides. We recently developed a separation strategy based on a combination of cation exchange and extraction chromatography to isolate and purify 225Ac. In this study, actinium and lanthanide equilibrium distribution coefficients and column elution behavior for both TODGA (N,N,N',N'-tetra-n-octyldiglycolamide) and TEHDGA (N,N,N',N'-tetrakis-2-ethylhexyldiglycolamide) were determined. Density functional theory (DFT) calculations were performed and were in agreement with experimental observations providing the foundation for understanding of the selectivity for Ac and lanthanides on different DGA (diglycolamide) based resins. The results of Gibbs energy (ΔGaq) calculations confirm significantly higher selectivity of DGA based resins for LnIII over AcIII in the presence of nitrate. DFT calculations and experimental results reveal that Ac chemistry cannot be predicted from lanthanide behavior under comparable circumstances.

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.

Tailoring medium energy proton beam to induce low energy nuclear reactions in 86SrCl2 for production of PET radioisotope 86Y.

This paper reports results of experiments at Brookhaven Linac Isotope Producer (BLIP) aiming to investigate effective production of positron emitting radioisotope (86)Y by the low energy (86)Sr(p,n) reaction. BLIP is a facility at Brookhaven National Laboratory designed for the proton irradiation of the targets for isotope production at high and intermediate proton energies. The proton beam is delivered by the Linear Accelerator (LINAC) whose incident energy is tunable from 200 to 66 MeV in approximately 21 MeV increments. The array was designed to ensure energy degradation from 66 MeV down to less than 20 MeV. Aluminum slabs were used to degrade the proton energy down to the required range. The production yield of (86)Y (1.2+/-0.1 mCi (44.4+/-3.7) MBq/µAh) and ratio of radioisotopic impurities was determined by assaying an aliquot of the irradiated (86)SrCl2 solution by gamma spectroscopy. The analysis of energy dependence of the (86)Y production yield and the ratios of radioisotopic impurities has been used to adjust degrader thickness. Experimental data showed substantial discrepancies in actual energy propagation compared to energy loss calculations.

Development of a large scale production of 67Cu from 68Zn at the high energy proton accelerator: closing the 68Zn cycle.

A number of research irradiations of (68)Zn was carried out at Brookhaven Linac Isotope Producer aiming to develop a practical approach to produce the radioisotope (67)Cu through the high energy (68)Zn(p,2p)(67)Cu reaction. Disks of enriched zinc were prepared by electrodeposition of (68)Zn on aluminum or titanium substrate and isolated in the aluminum capsule for irradition. Irradiations were carried out with 128, 105 and 92 MeV protons for at least 24h. After irradiation the disk was chemically processed to measure production yield and specific activity of (67)Cu and to reclaim the target material. The recovered (68)Zn was irradiated and processed again. The chemical procedure comprised BioRad cation exchange, Chelex-100 and anion exchange columns. Reduction of the oxidation degree of copper allowed for more efficient Cu/Co/Zn separation on the anion exchange column. No radionuclides other than copper isotopes were detected in the final product. The chemical yield of (67)Cu reached 92-95% under remote handling conditions in a hot box. Production yield of (67)Cu averaged 29.2 µCi/[µA-h×g (68)Zn] (1.08MBq/[µA-h×g (68)Zn]) in 24h irradiations. The best specific activity achieved was 18.6 mCi/µg (688.2 MBq/µg).

Activation of natural Hf and Ta in relation to the production of 177Lu.

The isotope (177)Lu is used in nuclear medicine and biology for in vivo applications as a radioactive label of various targeting agents. To extend the availability of no-carrier added (177)Lu, we investigated the feasibility of its production in a proton accelerator. Tantalum and Hf targets were irradiated and chemically processed to determine the radioisotope yield and cross-sections. The largest cross-sections (approximately 20 mb) were found for the Hf target at 195 MeV; however, the presence of co-produced Lu isotopes may limit the product applications. The results are in good agreement with theoretical data calculated using computer codes MCNPX and ORIGEN2S. Production of relevant medical isotopes such as (167)Tm and (169)Yb from the above targets is discussed as well.

DOTP-manganese and -nickel complexes: from a tetrahedral network with 12-membered rings to an ionic phosphonate.

DOTP (1,4,7,10-tetrakis(methylenephosphonic acid)-1,4,7,10-tetraazacyclododecane) was reacted hydrothermally with MnCl(2).2H(2)O and Ni(NO(3))(2).6H(2)O resulting in two structurally different compounds. Mn[C(3)NH(7)(PO(3)H(0.5))](4) crystallizes in the tetragonal space group P4/ncc, with a = 12.349(2) A, b = 12.349(2) A, c = 14.066(4) A, V = 2144.9(8) A(3), and Z = 4. Manganese atoms are tetrahedrally bonded by four phosphonate oxygen atoms from four equivalent ligands. All 12-membered macrocycles are connected in a "zigzag" manner by sharing manganese atoms and forming 22-membered cavities between each pair of two adjacent macrocycles. Ni[C(3)NH(6)(PO(3)H)](4)[Ni(H(2)O)(6)] crystallizes as an ion pair complex. Ni(1) is octahedrally coordinated to two pendent phosphonate oxygen atoms and four nitrogen atoms from the macrocyclic backbone. Ni(2) is surrounded by six coordinatedly bonded water molecules to form a hexaqua cation. The manganese complex shows ion exchange capability for Cs(+).

Cobalt phosphonates: an unusual polymeric cobalt phosphonate containing a clathrated phosphonate anion and a layered bisphosphonate.

Novel cobalt phosphonates [Co(H(2)O)(4)(H(4)L)][H(2)L].2H(2)O, 1, and Co(2)(H(2)O)(2)(L), 2, have been synthesized from 1,8-octylenediphosphonic acid (H(4)L). 1 has been fully characterized by X-ray single-crystal data, TGA, IR spectroscopy, and chemical analysis. The compound crystallizes in the triclinic space group P1 with a = 5.5415(8) A, b = 8.6382(8) A, c = 16.794 (2) A, alpha = 87.694(2) degrees, beta = 80.859(2) degrees, gamma = 76.005(2) degrees, V = 770.11(19) A(3), and Z = 1. A cobalt atom lies in the center of symmetry and is octahedrally coordinated by two oxygen atoms from two undissociated diphosphonic ligands H(4)L and four molecules of water. The cobalt atom and undissociated ligand H(4)L are combined to form polymeric chains along the c-axis, resulting in the formation of a one-dimensional framework. The positive charge on the cobalt atom remains upon coordination and is balanced by a negatively charged uncoordinated ligand (H(2)L) found as a clathrate in the lattice. Two lattice water molecules, hydrogen-bonded with the coordinated and uncoordinated ligands, complete the structure. The metal phosphonate chains are held together and bridge the uncoordinated anionic ligands by a number of strong hydrogen bonds, which make the structure possible. Cobalt phosphonate 2 has been characterized by TGA measurements, IR spectroscopy, and chemical analysis. The compound has a layered structure with an interlayer spacing of 14.26 A. Metal phosphonate layers are cross-linked by hydrocarbon chains. The water molecules are coordinated to the metal atom. According to IR data, compound 2 contains two equivalent PO bonds and one different PO bond, which may be a result of the different types of Co-O-P connectivity within one phosphonic group.