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  1. Demonstration of a 228Ra/228Ac isotope generator

    An isotope generator to produce 228Ac from 228Ra was developed using a cation exchange resin column eluted with an acetate-diethylenetriaminpentaacetic acid buffer. Here, the elution behavior of 228Ac on the column was studied with solutions of various pHs to select the optimal conditions. Two identical isotope generators were eluted for 47 days with over 100 mL of eluant with no detectable 228Ra breakthrough and high 228Ac yields (∼95%). The separation requires only biocompatible reagents and is performed at pH 4.6, conditions suitable for radiopharmaceutical studies of Ac.
  2. Cation exchange separation of radium and actinium using lactic acid DTPA buffer

    The separation of actinium (228Ac) from radium (223,228Ra) on cation exchange resin with a diethylenetriaminpentaacetic acid-lactate buffer solution is demonstrated with series of columns. High yield, high radiopurity (~ 100%) separations of Ac from Ra are feasible with small columns in biologically compatible conditions and pHs. As Ac is eluted before Ra on these columns, further studies were performed to determine if this separation system could be applied to Ra/Ac isotope generators, but these were not successful. In conclusion, the separations presented in this work may be relevant for radiopharmaceutical purifications of 225Ac which is typically obtained from its 225Ramore » parent isotope.« less
  3. Transport model predictions of 225Ac production cross sections via energetic p, d and α irradiation of 232Th targets

    Monte Carlo transport codes PHITS and MCNP6 were used to calculate the production cross sections of 225,227Ac, 227,229Th, 223,225Ra, and 229,230,231Pa via the bombardment of a 232Th target with energetic protons, deuterons, and α-particles. The incident projectile energies ranged between 10 and 800 MeV/nucleon. When possible, the predicted production cross sections were compared with the available experimental data and other predictions. Here, the degree of the codes’ abilities to match the measured data provides a qualitative assessment of the codes’ abilities to predict data from similar, but unmeasured, projectile/target systems. In addition, a comparison between calculated cross sections and datamore » may provide insight into possible improvements in the physics models employed by those transport codes.« less
  4. Spectroscopic study and lifetime measurement of the 6d7p 3F2o state of radium

    We report a method for the precision measurement of the oscillator strengths and the branching fractions of the decay channels of the 6d7p 3F2o state in 226Ra. Here, this method exploits a set of metastable states present in Ra, allowing a measurement of the oscillator strengths that does not require knowledge of the number of atoms in the atomic beam. We measure the oscillator strengths and the branching fractions for decays from the 6d7p 3F2o state to the 7s6d 3D1, 7s6d 3D2, and 7s6d 1D2 states and constrain the branching fraction to the 7s6d 3D3 state to be less thanmore » 0.4% (68% confidence limit). The lifetime of the 3F2o state is determined to be 15 ± 4 ns.« less
  5. 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 exchangemore » 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).« less
  6. Radium-226 analysis methodology in Savannah River Site high activity waste matrices

    Waste cleanup efforts currently underway at the Savannah River Site have created a need to characterize Radium-226 levels in the various high activity waste matrices currently in Site inventories. Here, the traditional method our laboratory used for analyzing Ra-226 in higher activity matrices was based on classic cation exchange methodology. Radiochemical separations were often initiated in remotely operated shielded analytical cells followed by additional hands-on separations in radiological hoods. Methodology based on IBC advanced technologies SuperLig 640 extractant, mounted in 3M Empore filter media has been developed to streamLine the radium analyses.

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