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Sample records for perrhenates

  1. Dymethyl sulfoxide complexes of rare earth perrhenates

    International Nuclear Information System (INIS)

    Osorio, V.K.L.; Kawano, Y.; Kuya, M.K.; Perrier, M.

    1980-01-01

    The complexes Ln(ReO 4 ) 3 .8dmso (Ln = La-Lu, Y) and La(ReO 4 ) 3 .8dmso-d 6 have been prepared and characterized by conductance, infrared and Raman measurements. All the complexes have structures involving complex cation and non-coordinated anions in the solid state. The conductance values in nitromethane solution indicate a behavior near to a 1:1 electrolyte type. A comparative study with the data accumulated on the literature shows that perrhenate anion has higher coordinating capacity than perchlorate and hexafluorophosphate ones. (Author) [pt

  2. Cyclohexanone microfluidic extraction of radioactive perrhenate from acid solutions

    Energy Technology Data Exchange (ETDEWEB)

    Dalmázio, Ilza [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil); Oehlke, Elisabeth, E-mail: E.Oehlke@tudelft.nl [Section Radiation and Isotopes for Health, Department of Radiation Science and Technology, Delft University of Technology (Netherlands)

    2017-07-01

    Several studies have investigated the application of microfluidic devices in extraction processes. A potential use of microfluidic devices is in radionuclide generators based on solvent extraction, as the {sup 188}W/{sup 188}Re generator. The aim of this work is to present the initial results of microfluidic solvent extraction of radioactive perrhenate. Aqueous solutions of ammonium perrhenate at 0.1 mg/mL (in water, HCl or sodium tungstate) were used as feed solution and cyclohexanone as extractant. As a first step, the fluid behaviour inside the glass microchannel was evaluated to reach laminar flow. The second step was the determination of extraction efficiency using thermal neutron activated perrhenate to produce feed solutions. The extraction conditions permitted liquid-liquid contact times as short as 0.5 s. Increasing of the contact time, resulted in a higher extraction efficiency of perrhenate, e.g. 14 % for 0.5 s and 32 % for 1.1 s using a 0.1 mol/L HCl feed solution. The extraction of perrhenate improved also when applying a feed solution with higher acidity, e.g. 52% for 1 mol/L HCl with contact time of 1.1 s. The influence of adding sodium tungstate to the feed solution was also examined. To the best of our knowledge, these are the first results related to perrhenate solvent extraction using a microfluidic device. The usefulness of microfluidic devices to screen extraction conditions was demonstrated making it possible to evaluate the effect of electrolytes on the perrhenate extraction process in a short time-frame. (author)

  3. Cyclohexanone microfluidic extraction of radioactive perrhenate from acid solutions

    International Nuclear Information System (INIS)

    Dalmázio, Ilza; Oehlke, Elisabeth

    2017-01-01

    Several studies have investigated the application of microfluidic devices in extraction processes. A potential use of microfluidic devices is in radionuclide generators based on solvent extraction, as the 188 W/ 188 Re generator. The aim of this work is to present the initial results of microfluidic solvent extraction of radioactive perrhenate. Aqueous solutions of ammonium perrhenate at 0.1 mg/mL (in water, HCl or sodium tungstate) were used as feed solution and cyclohexanone as extractant. As a first step, the fluid behaviour inside the glass microchannel was evaluated to reach laminar flow. The second step was the determination of extraction efficiency using thermal neutron activated perrhenate to produce feed solutions. The extraction conditions permitted liquid-liquid contact times as short as 0.5 s. Increasing of the contact time, resulted in a higher extraction efficiency of perrhenate, e.g. 14 % for 0.5 s and 32 % for 1.1 s using a 0.1 mol/L HCl feed solution. The extraction of perrhenate improved also when applying a feed solution with higher acidity, e.g. 52% for 1 mol/L HCl with contact time of 1.1 s. The influence of adding sodium tungstate to the feed solution was also examined. To the best of our knowledge, these are the first results related to perrhenate solvent extraction using a microfluidic device. The usefulness of microfluidic devices to screen extraction conditions was demonstrated making it possible to evaluate the effect of electrolytes on the perrhenate extraction process in a short time-frame. (author)

  4. The effect of gaseous ammonia on cobalt perrhenate

    International Nuclear Information System (INIS)

    Maslov, L.P.; Men'shikov, O.D.; Borisov, V.V.; Sorokin, S.I.; Krutovertsev, S.A.; Kharkevich, S.I.; Ivanova, O.M.

    1994-01-01

    The influence of humid air ammonia mixture on crystal pentahydrate of cobalt(2) perrhenate has been studied by the methods of PES, IR spectroscopy thermal analysis and electrophysical measurements. It is shown that with an increase in ammonia content in gaseous phase cobalt perrhenate successively transforms into diaquodiammine-, tetrammine- and μ-dioxo-bis-(tetrammine) derivatives of cobalt. Reversibility of dioxocomplex formation and a correlation between the change in electrophysical properties of crystal sample and change in ammonia content in gaseous phase are pointed out. 16 refs.; 4 figs.; 1 tab

  5. Study of pertechnetate and perrhenate of calcium using infrared spectroscopy and PMR methods

    International Nuclear Information System (INIS)

    Teterin, Eh.G.; Zajtseva, L.L.; Samsonov, V.E.; Aksenenko, A.V.

    1986-01-01

    PMR and IR spectroscopic study of hydrates of calcium pertechnetate and perrhenates is carried out and their dehydration is studied. IR spectra analysis showed that dihydrates of calcium pertechnetate and perrhenate possess two types of crystal water molecules to which in spectra two sets of valence and deformation vibration bands and at least two types of pertechnetate and perrhenate groups correspond. During dehydration of calcium perrhenate dihydrate to monohydrate one type bond water molecules are withdrawn. The band set characteristic of the second type bond disappears only at complete dehydration of perrhenate, followed by spectrum simplification also in the region of perrhenate group absorption. Change of interproton distance in crystal water molecules under the action of crystal field, modifying during dehydration of calcium perrhenate dihydrate, is detected using PMR method

  6. Addition compounds of yttrium and lanthanide perrhenates with tetramethylene sulphoxide

    International Nuclear Information System (INIS)

    Umeda, K.

    1977-01-01

    Adducts of lanthanide perrhenates with tetramethylene sulfoxide are prepared and characterized. The compounds having as general formula Ln(Re04) 3 .7.5 TMSO(ln=La-Lu and Y) are characterized by elemental analysis, infrared spectra, molar conductance measurements, x-ray powder patterns, differential scanning calorimetry curves, melting temperature range measurements and thermogravimetric analysis [pt

  7. Solution and solid-phase halogen and C-H hydrogen bonding to perrhenate.

    Science.gov (United States)

    Massena, Casey J; Riel, Asia Marie S; Neuhaus, George F; Decato, Daniel A; Berryman, Orion B

    2015-01-28

    (1)H NMR spectroscopic and X-ray crystallographic investigations of a 1,3-bis(4-ethynyl-3-iodopyridinium)benzene scaffold with perrhenate reveal strong halogen bonding in solution, and bidentate association in the solid state. A nearly isostructural host molecule demonstrates significant C-H hydrogen bonding to perrhenate in the same phases.

  8. Temperatures and enthalpies of melting of alkali-metal perrhenates

    International Nuclear Information System (INIS)

    Lukas, W.; Gaune-Escard, M.

    1982-01-01

    Melting temperatures and enthalpies of melting were determined for alkali-metal perrhenates by differential enthalpic analysis using a high-temperature Calvet microcalorimeter. The following values were obtained: for LiReO 4 : 692 K and 24.9 kJ.mol -1 ; for NaReO 4 : 693 K and 33 kJ.mol -1 ; for KReO 4 : 828 K and 36 kJ.mol -1 ; for RbReO 4 : 878 K and 34 kJ.mol -1 ; for CsReO 4 : 893 K and 34 kJ.mol -1 . (author)

  9. Selective Extraction of Perrhenate and Pertechnetate by New Macrocyclic Compounds

    Energy Technology Data Exchange (ETDEWEB)

    Paviet-Hartmann, Patricia; Horkley, Jared; Wolfrom, Earle [Idaho State University/Idaho National Laboratory, 1776 Science Center Drive, Idaho Falls, ID 83402 (United States); Pak, Joshua [Idaho State University, 921 S. 8th Avenue, Pocatello, ID 83209 (United States)

    2008-07-01

    The long half-life of technetium-99 and its ability to form an anionic species makes it a major concern when considering long-term disposal of high-level radioactive waste. Furthermore, as its most stable species in the environment, the pertechnetate ion, TcO{sub 4}{sup -} is highly mobile and is considered as a long-term hazard in nuclear waste disposal. There is a need for the development of new extractant systems, such as systems based on crown ethers that may serve to selectively extract and separate this long lived radionuclide from different streams for potential industrial application. In this paper, we are reporting the design and synthesis of new macrocyclic compounds to selectively extract technetium and rhenium from complex mixtures. Preliminary tests performed for the selective extraction of pertechnetate and perrhenate are presented. (authors)

  10. Selective Extraction of Perrhenate and Pertechnetate by New Macrocyclic Compounds

    International Nuclear Information System (INIS)

    Paviet-Hartmann, Patricia; Horkley, Jared; Wolfrom, Earle; Pak, Joshua

    2008-01-01

    The long half-life of technetium-99 and its ability to form an anionic species makes it a major concern when considering long-term disposal of high-level radioactive waste. Furthermore, as its most stable species in the environment, the pertechnetate ion, TcO 4 - is highly mobile and is considered as a long-term hazard in nuclear waste disposal. There is a need for the development of new extractant systems, such as systems based on crown ethers that may serve to selectively extract and separate this long lived radionuclide from different streams for potential industrial application. In this paper, we are reporting the design and synthesis of new macrocyclic compounds to selectively extract technetium and rhenium from complex mixtures. Preliminary tests performed for the selective extraction of pertechnetate and perrhenate are presented. (authors)

  11. Hydrolysis of cellulose catalyzed by quaternary ammonium perrhenates in 1-allyl-3-methylimidazolium chloride.

    Science.gov (United States)

    Wang, Jingyun; Zhou, Mingdong; Yuan, Yuguo; Zhang, Quan; Fang, Xiangchen; Zang, Shuliang

    2015-12-01

    Quaternary ammonium perrhenates were applied as catalyst to promote the hydrolysis of cellulose in 1-allyl-3-methylimidazolium chloride ([Amim]Cl). The quaternary ammonium perrhenates displayed good catalytic performance for cellulose hydrolysis. Water was also proven to be effective to promote cellulose hydrolysis. Accordingly, 97% of total reduced sugar (TRS) and 42% of glucose yields could be obtained under the condition of using 5mol% of tetramethyl ammonium perrhenate as catalyst, 70μL of water, ca. 0.6mmol of microcrystalline cellulose (MCC) and 2.0g of [Amim]Cl as solvent under microwave irradiation for 30min at 150°C (optimal conditions). The influence of quaternary ammonium cation on the efficiency of cellulose hydrolysis was examined based on different cation structures of perrhenates. The mechanism on perrhenate catalyzed cellulose hydrolysis is also discussed, whereas hydrogen bonding between ReO4 anion and hydroxyl groups of cellulose is assumed to be the key step for depolymerization of cellulose. Copyright © 2015. Published by Elsevier Ltd.

  12. Study of oxygenated compounds of rhenium VII: actinide perrhenates, molybdo- and tungstoperrhenates

    International Nuclear Information System (INIS)

    Silvestre, J.-P.

    1978-01-01

    Crystallographic data for the perrhenates of the actinides and their hydrates. Study of the thermal stability of the perrhenates of the actinides. Double perrhenates of thorium and monovalent elements: Th 5 M 2 (ReO 4 ) 22 , ThM(ReO 4 ) 5 , ThM 2 (ReO 4 ) 6 with M = Na, K, Rb, Cs and Tl; ThM 3 (ReO 4 ) 7 with M=K, Rb, Cs and Tl are showing up in the study of the systems Th(ReO 4 ) 4 -M(ReO 4 ). Study of the possibilities of substitution Re 7+ -Mo 6+ and Re 7+ -W 6+ : non stoechiometric cubic compounds Thsub(1/2-x/4)(Msub(1-x)Resub(x)O 4 ) with 1/6 3 (MO 4 )(ReO 4 ) (M = Mo, W) are disclosed [fr

  13. A new series of rhenium VII compounds: sodium-rare earth perrhenates

    International Nuclear Information System (INIS)

    Slimane, Z.A.A.; Silvestre, J.-P.; Freundlich, William

    1978-01-01

    Synthesis by solid state reaction or in aqueous solution and radiocrystallographical study of the hexagonal sodium-rare earth perrhenates NaLn(ReO 4 ) 4 (Ln=La, Nd, Sm, Eu, Gd, Er) and of the tetragonal tetrahydrates NaLn(ReO 4 ) 4 , 4H 2 O (Ln=Eu, Gd, Er, Lu) [fr

  14. Transuranium perrhenates: Np(IV), Pu(IV) and (III), Am (III)

    International Nuclear Information System (INIS)

    Silvestre, Jean-Paul; Freundlich, William; Pages, Monique

    1977-01-01

    Synthesis in aqueous solution and by solid state reactions, crystallographical characterization and study of the stability of some transuranium perrhenates: Asup(n+)(ReO 4 - )sub(n) (A=Np(IV), Pu(IV), Pu(III), Am(III) [fr

  15. Room temperature synthesis of ReS2 through aqueous perrhenate sulfidation

    Science.gov (United States)

    Borowiec, Joanna; Gillin, William P.; Willis, Maureen A. C.; Boi, Filippo S.; He, Y.; Wen, J. Q.; Wang, S. L.; Schulz, Leander

    2018-02-01

    In this study, a direct sulfidation reaction of ammonium perrhenate (NH4ReO4) leading to a synthesis of rhenium disulfide (ReS2) is demonstrated. These findings reveal the first example of a simplistic bottom-up approach to the chemical synthesis of crystalline ReS2. The reaction presented here takes place at room temperature, in an ambient and solvent-free environment and without the necessity of a catalyst. The atomic composition and structure of the as-synthesized product were characterized using several analysis techniques including energy dispersive x-ray spectroscopy, x-ray photoelectron spectroscopy, x-ray diffraction, transmission electron microscopy, Raman spectroscopy, thermogravimetric analysis and differential scanning calorimetry. The results indicated the formation of a lower symmetry (1Tʹ) ReS2 with a low degree of layer stacking.

  16. Zirconium-Based Metal–Organic Framework for Removal of Perrhenate from Water

    Energy Technology Data Exchange (ETDEWEB)

    Banerjee, Debasis; Xu, Wenqian; Nie, Zimin; Johnson, Lewis E. V.; Coghlan, Campbell; Sushko, Maria L.; Kim, Dongsang; Schweiger, Michael J.; Kruger, Albert A.; Doonan, Christian J.; Thallapally, Praveen K.

    2016-09-06

    Efficient removal of pertechnetate (TcO4-) anions from liquid waste or melter off-gas solution for alternative treatment is one of the promising options to manage 99Tc in legacy nuclear waste. Safe immobilization of 99Tc is of major importance due to its long half-life (t1/2= 2.13 × 105 yrs) and environmental mobility. Different types of inorganic and solid state ion-exchange materials such as layered double hydroxides have been shown to absorb TcO4- anions from water. However, both high capacity and selectivity have yet to be achieved in a single material. Herein, we show that a protonated version of an ultra-stable zirconium based metal-organic framework can adsorb perrhenate (ReO4-) anions, a non-radioactive sur-rogate for TcO4-, from water even in the presence of other common anions. Synchrotron based powder X-ray diffraction and molecular simulations were used to identify the position of the adsorbed ReO4- (surrogate for TcO4-) molecule within the framework.

  17. Zirconium-Based Metal–Organic Framework for Removal of Perrhenate from Water

    Energy Technology Data Exchange (ETDEWEB)

    Banerjee, Debasis; Xu, Wenqian; Nie, Zimin; Johnson, Lewis E. V.; Coghlan, Campbell; Sushko, Maria L.; Kim, Dongsang; Schweiger, Michael J.; Kruger, Albert A.; Doonan, Christian J.; Thallapally, Praveen K.

    2016-09-06

    Efficient removal of pertechnetate (TcO4 -) anions from liquid waste or melter off-gas solution for alternative treatment is one of the promising options to manage 99Tc in legacy nuclear waste. Safe immobilization of 99Tc is of major importance due to its long half-life (t1/2= 2.13 × 105 yrs) and environmental mobility. Different types of inorganic and solid state ion-exchange materials such as layered double hydroxides have been shown to absorb TcO4 - anions from water. However, both high capacity and selectivity have yet to be achieved in a single material. Herein, we show that a protonated version of an ultra-stable zirconium based metalorganic framework can adsorb perrhenate (ReO4 -) anions, a non-radioactive surrogate for TcO4 -, from water even in the presence of other common anions. Synchrotron based powder X-ray diffraction and molecular simulations were used to identify the position of the adsorbed ReO4 - (surrogate for TcO4 -) molecule within the framework.

  18. Room temperature synthesis of ReS2 through aqueous perrhenate sulfidation.

    Science.gov (United States)

    Borowiec, Joanna; Gillin, William P; Willis, Maureen; Boi, Filippo; He, Yi; Wen, Jiqiu; Wang, Shanling; Schulz, Leander

    2017-12-29

    In this study, a direct sulfidation reaction of ammonium perrhenate (NH4ReO4) leading to a synthesis of rhenium disulfide (ReS2) is demonstrated. These finding reveal the first example of a simplistic bottom-up approach to the chemical synthesis of crystalline ReS2. The reaction presented here takes place at room temperature, in an ambient and solvent-free environment and without the necessity of a catalyst. The atomic composition and structure of the as-synthesized product were characterized using several analysis techniques including energy dispersive X-ray (EDX) spectroscopy, X-ray photoelectron spectroscopy (XPS), X-ray diffraction (XRD), transmission electron microscopy (TEM), Raman spectroscopy, thermogravimetric analysis (TGA) and differential scannig calorimetry (DSC). The results indicated the formation of a lower symmetry (1Td) ReS2 with a low degree of layer stacking. © 2017 IOP Publishing Ltd.

  19. Perrhenate sorption kinetics in zerovalent iron in high pH and nitrate media

    International Nuclear Information System (INIS)

    Lenell, Brian A.; Arai, Yuji

    2017-01-01

    Graphical abstract: Ammonium adsorption enhanced ReO 4 − adsorption in ZVI under alkaline conditions (modified from Cho et al., 2015) [39]. - Highlights: • ZVI effectively sorbs Re(VII) at near neutral pH. • Sorption of Re(VII) in ZVI is attributed to the reductive precipitation of Re(IV)O 2 . • The extent of Re(VII) sorption in ZVI decreases with increasing pH from 8 to 10. • The rate of Re(VII) sorption in ZVI increases with increasing nitrate concentration. - Abstract: Technetium(Tc)-99 is one of major risk drivers in low level radioactive liquid waste at the U.S. Department of Energy sites. Cementitious waste technology (CWT) has been considered immobilizing pertechnetate, Tc(VII)O 4 − , in brine and alkaline waste solutions, as Tc(IV) oxides and/or sulfides with the use of reducing agents like slag. In this study, zero valent iron (ZVI) was evaluated as a potential reducing agent in CWT as a function of pH and [nitrate] (0–0.1 M) using perrhenate, Re(VII)O 4 − , as an analogue for Tc(VII)O 4 − . Batch Re(VII)O 4 − sorption experiments in conjunction with X-ray absorption spectroscopic analysis showed that the Re(VII) sorption occurred via the reductive precipitation of Re(IV)O 2 (s) and the extent of sorption decreased with increasing pH from 8 to 10. Interestingly, pseudo 2nd order kinetic rates increased with increasing [nitrate] which was attributed to co-adsorption of NH 4 + (i.e., a reaction product of reduced nitrate by ZVI), facilitating electrostatic attraction towards ReO 4 − under alkaline conditions. Considering the thermodynamically favorable reduction of Tc(VII) over Re(VII), ZVI might have potential for improving the reduction capacity of the current CWT.

  20. Radiation absorbed doses in the event of balloon rupture (BR) during endovascular brachytherapy (EB) using 188Re-perrhenate

    International Nuclear Information System (INIS)

    Angelides, S.; Hetherington, E.; Karolis, C.; Walker, B.; Jackson, T.; Knittel, T.; Friend, C.; Pitney, M.; Jepson, N.; Milross, C.; Lonergan, D.

    2000-01-01

    Full text: endovascular brachytherapy (EB) using liquid or solid radiation sources, is an effective emerging therapy for coronary artery disease. Liquid sources provide uniform radiation dose to the vessel wall. However the radiation burden in the unlikely event of BR is not insignificant. The aims of this study were to determine i) absorbed dose for various 188 Re radiopharmaceuticals in the event of BR, and ii) effects of thyroid uptake blocking agent, Lugol's iodine (Ll) and/or bladder catheterisation (BC). Dose calculations were based on MIRDOSE 3.1 with dynamic bladder model and MIRD Dose Estimate Report No.8 for 99 Tc m -pertechnetate, which has similar biokinetic properties to 188 Re-perrhenate. Normal renal function and a bladder voiding interval of 4.8h (1 minute with catheter) were assumed. BR was simulated ex-vivo by puncturing a Solaris angioplasty balloon filled with normal saline at 4 atm. LI, MAG3 and DTPA substantially reduces the radiation dose following BR, particularly to the thyroid, and BC reduces the bladder wall dose. Only the contents of the balloon leaked; 0.4 ml of the total volume of 1.8ml. As binding of 188 Re to ligands is cumbersome, we opted to use LI. Twenty five patients with in-stent re-stenosis have been treated using 188 Re-perrhenate (8 GBq/ml), with no BR. Copyright (2000) The Australian and New Zealand Society of Nuclear Medicine Inc

  1. Perrhenate sorption kinetics in zerovalent iron in high pH and nitrate media

    Energy Technology Data Exchange (ETDEWEB)

    Lenell, Brian A.; Arai, Yuji, E-mail: yarai@illinois.edu

    2017-01-05

    Graphical abstract: Ammonium adsorption enhanced ReO{sub 4}{sup −} adsorption in ZVI under alkaline conditions (modified from Cho et al., 2015) [39]. - Highlights: • ZVI effectively sorbs Re(VII) at near neutral pH. • Sorption of Re(VII) in ZVI is attributed to the reductive precipitation of Re(IV)O{sub 2}. • The extent of Re(VII) sorption in ZVI decreases with increasing pH from 8 to 10. • The rate of Re(VII) sorption in ZVI increases with increasing nitrate concentration. - Abstract: Technetium(Tc)-99 is one of major risk drivers in low level radioactive liquid waste at the U.S. Department of Energy sites. Cementitious waste technology (CWT) has been considered immobilizing pertechnetate, Tc(VII)O{sub 4}{sup −}, in brine and alkaline waste solutions, as Tc(IV) oxides and/or sulfides with the use of reducing agents like slag. In this study, zero valent iron (ZVI) was evaluated as a potential reducing agent in CWT as a function of pH and [nitrate] (0–0.1 M) using perrhenate, Re(VII)O{sub 4}{sup −}, as an analogue for Tc(VII)O{sub 4}{sup −}. Batch Re(VII)O{sub 4}{sup −} sorption experiments in conjunction with X-ray absorption spectroscopic analysis showed that the Re(VII) sorption occurred via the reductive precipitation of Re(IV)O{sub 2}(s) and the extent of sorption decreased with increasing pH from 8 to 10. Interestingly, pseudo 2nd order kinetic rates increased with increasing [nitrate] which was attributed to co-adsorption of NH{sub 4}{sup +} (i.e., a reaction product of reduced nitrate by ZVI), facilitating electrostatic attraction towards ReO{sub 4}{sup −} under alkaline conditions. Considering the thermodynamically favorable reduction of Tc(VII) over Re(VII), ZVI might have potential for improving the reduction capacity of the current CWT.

  2. Experimental determination of the speciation, partitioning, and release of perrhenate as a chemical surrogate for pertechnetate from a sodalite-bearing multiphase ceramic waste form

    Energy Technology Data Exchange (ETDEWEB)

    Pierce, Eric M.; Lukens, Wayne W.; Fitts, Jeff. P.; Jantzen, Carol. M.; Tang, G.

    2013-12-01

    A key component to closing the nuclear fuel cycle is the storage and disposition of nuclear waste in geologic systems. Multiphase ceramic waste forms have been studied extensively as a potential host matrix for nuclear waste. Understanding the speciation, partitioning, and release behavior of radionuclides immobilized in multiphase ceramic waste forms is a critical aspect of developing the scientific and technical basis for nuclear waste management. In this study, we evaluated a sodalite-bearing multiphase ceramic waste form (i.e., fluidized-bed steam reform sodium aluminosilicate [FBSR NAS] product) as a potential host matrix for long-lived radionuclides, such as technetium (99Tc). The FBSR NAS material consists primarily of nepheline (ideally NaAlSiO4), anion-bearing sodalites (ideally M8[Al6Si6O24]X2, where M refers to alkali and alkaline earth cations and X refers to monovalent anions), and nosean (ideally Na8[AlSiO4]6SO4). Bulk X-ray absorption fine structure analysis of the multiphase ceramic waste form, suggest rhenium (Re) is in the Re(VII) oxidation state and has partitioned to a Re-bearing sodalite phase (most likely a perrhenate sodalite Na8[Al6Si6O24](ReO4)2). Rhenium was added as a chemical surrogate for 99Tc during the FBSR NAS synthesis process. The weathering behavior of the FBSR NAS material was evaluated under hydraulically unsaturated conditions with deionized water at 90 ?C. The steady-state Al, Na, and Si concentrations suggests the weathering mechanisms are consistent with what has been observed for other aluminosilicate minerals and include a combination of ion exchange, network hydrolysis, and the formation of an enriched-silica surface layer or phase. The steady-state S and Re concentrations are within an order of magnitude of the nosean and perrhenate sodalite solubility, respectively. The order of magnitude difference between the observed and predicted concentration for Re and S may be associated with the fact that the anion

  3. Oxidation of 5,6-diamino-1,3-dimethyl-2,4-dioxopyrimidine by perrhenate: the crystal structure of 1,3,6,8-tetramethylpyrimidopteridine-2,4,5,7-tetrone

    International Nuclear Information System (INIS)

    Booysen, Irvin; Gerber, Thomas I.A.; Mayer, Peter

    2008-01-01

    The oxidation of 5,6-diamino-1,3-dimethyl-2,4-dioxopyrimidine (H 2 ddd) by perrhenate (ReO 4 - ) led to the formation of 1,3-dimethylalloxan, which condenses with unoxidized H 2 ddd to yield the product 1,3,6,8-tetramethylpyrimidopteridine-2,4,5,7-tetrone (tppt). The structure of tppt consists of a central pyrazine ring and two terminal pyrimidine rings in cis positions. The dihedral angles between the pyrazine and pyrimidine rings are 1.08 deg and 1.20 deg. (author)

  4. Experimental determination of the speciation, partitioning, and release of perrhenate as a chemical surrogate for pertechnetate from a sodalite-bearing multiphase ceramic waste form

    International Nuclear Information System (INIS)

    Pierce, E.M.; Lukens, W.W.; Fitts, J.P.; Jantzen, C.M.; Tang, G.

    2014-01-01

    Highlights: • Multiphase ceramic waste form is composed of primarily of nepheline, nosean, and sodalite. • Rhenium is in the 7+ oxidation state and has partitioned to a mixed Re-bearing sodalite phase. • Mechanism of corrosion for the multiphase matrix is similar to other silicate minerals. • A mixed-anion sodalite phases controls Re release in the multiphase waste forms. - Abstract: A key component to closing the nuclear fuel cycle is the storage and disposition of nuclear waste in geologic systems. Multiphase ceramic waste forms have been studied extensively as a potential host matrix for nuclear waste. Understanding the speciation, partitioning, and release behavior of radionuclides immobilized in multiphase ceramic waste forms is a critical aspect of developing the scientific and technical basis for nuclear waste management. In this study, we evaluated a sodalite-bearing multiphase ceramic waste form (i.e., fluidized-bed steam reform sodium aluminosilicate [FBSR NAS] product) as a potential host matrix for long-lived radionuclides, such as technetium ( 99 Tc). The FBSR NAS material consists primarily of nepheline (ideally NaAlSiO 4 ), anion-bearing sodalites (ideally M 8 [Al 6 Si 6 O 24 ]X 2 , where M refers to alkali and alkaline earth cations and X refers to monovalent anions), and nosean (ideally Na 8 [AlSiO 4 ] 6 SO 4 ). Bulk X-ray absorption fine structure analysis of the multiphase ceramic waste form, suggest rhenium (Re) is in the Re(VII) oxidation state and has partitioned to a Re-bearing sodalite phase (most likely a perrhenate sodalite Na 8 [Al 6 Si 6 O 24 ](ReO 4 ) 2 ). Rhenium was added as a chemical surrogate for 99 Tc during the FBSR NAS synthesis process. The weathering behavior of the FBSR NAS material was evaluated under hydraulically unsaturated conditions with deionized water at 90 °C. The steady-state Al, Na, and Si concentrations suggests the weathering mechanisms are consistent with what has been observed for other aluminosilicate

  5. G2 arrest and apoptosis of cultured Raji cells by continuous low dose rate beta irradiation therapy with 188Re-perrhenate

    International Nuclear Information System (INIS)

    Yim, S. J.; Kim, E. H.; Lee, T. S.; Woo, K. S.; Jeong, W. S.; Choi, C. W.; Yim, S. M.

    2001-01-01

    Beta emitting radionuclide therapy gives exponentially decreasing radiation dose rate and results in cell death presumably by apoptosis. We observed changes in DNA content and apoptosis in relatively low dose rate beta irradiation. Raji cells were cultured and incubated with 188Re-perrhenate (3.7MBq, or 370MBq/ml) for 4 hours to give irradiation dose of 0.4, 4, or 40 Gy. After changing the culture media, cells were cultured for 2,4,8,16, and 24 hours. The cells were stained with Trypan blue, Annexin-V and Propidium Iodide (PI) to observe cell viability, cell membrane alternation by apoptosis and changes in DNA content respectively. Flowcytometry was done for Annexin-V and PI to quantitate apoptosis and necrosis in the irradiated cells. DAPI(4,6-diamidino-2-phenylindole) stain was also done to observe the damage in the nucleus. Cell viability decreased with an increasing radiation dose. Cells irradiated in 40 Gy showed early uptake of both Annexin-V and PI suggesting cell death by necrosis. Cells irradiated in 0.4 Gy showed delayed uptake of Annexin-V only, and later on PI uptake suggesting cell death mainly by apoptosis. The cells irradiated in 0.4 Gy showed G2 arrest in 16 hours after irradiation, but the cells irradiated in 40 Gy showed early DNA fragmentation within 2 hours after irradiation. In DAPI stain, early nucleus damage was observed in the cells irradiated in 40 Gy. On the other hand, slowly increasing apoptotic bodies were observed in the cells irradiated in 0.4 Gy. These results suggest that continuous low-dose irradiation induces G2 arrest and progressive apoptosis in cells while continuous high-dose irradiation induces rapid necrosis. Therefore, we expect therapeutic effect by continuous low-dose rate irradiation with beta emitting radiopharmaceuticals

  6. Heterometallic cerium(IV) perrhenate, permanganate, and molybdate complexes supported by the imidodiphosphinate ligand [N(i-Pr2PO)2]-.

    Science.gov (United States)

    Wang, Guo-Cang; Sung, Herman H Y; Dai, Feng-Rong; Chiu, Wai-Hang; Wong, Wai-Yeung; Williams, Ian D; Leung, Wa-Hung

    2013-03-04

    Heterometallic cerium(IV) perrhenate, permanganate, and molybdate complexes containing the imidodiphosphinate ligand [N(i-Pr2PO)2](-) have been synthesized, and their reactivity was investigated. Treatment of Ce[N(i-Pr2PO)2]3Cl (1) with AgMO4 (M = Re, Mn) afforded Ce[N(i-Pr2PO)2]3(ReO4) (2) or Ce2[N(i-Pr2PO)2]6(MnO4)2 (3). In the solid state, 3 is composed of a [Ce2{N(i-Pr2PO)2}6(MnO4)](+) moiety featuring a weak Ce-OMn interaction [Ce-OMn distance = 2.528(8) Å] and a noncoordinating MnO4(-) counteranion. While 3 is stable in the solid state and acetonitrile solution, it decomposes readily in other organic solvents, such as CH2Cl2. 3 can oxidize ethylbenzene to acetophenone at room temperature. Treatment of 1 with AgBF4, followed by reaction with [n-Bu4N]2[MoO4], afforded [Ce{N(i-Pr2PO)2}3]2(μ-MoO4) (4). Reaction of trans-Ce[N(i-Pr2PO)2]2(NO3)2 (5), which was prepared from (NH4)2Ce(NO3)6 and K[N(i-Pr2PO)2], with 2 equiv of [n-Bu4N][Cp*MoO3] yielded trans-Ce[N(i-Pr2PO)2]2(Cp*MoO3)2 (6). 4 can catalyze the oxidation of methyl phenyl sulfide with tert-butyl hydroperoxide with high selectivity. The crystal structures of complexes 3-6 have been determined.

  7. EPR spectra of some irradiated polycrystalline perrhenate

    International Nuclear Information System (INIS)

    Zaitseva, N.G.; Constantinescu, M.; Georgescu, R.; Constantinescu, O.

    1978-10-01

    An EPR study of the paramagnetic centers formed by γ, electron and neutron irradiation of the NaReO 4 and KReO 4 was made. In the EPR spectra of the powder samples irradiated γ, with electrons and neutrons, the presence of three types of paramagnetic centers was observed. From the EPR parameters, the centers were attributed to the ReOsub(4)sup(.), ReOsub(3)sup(.) and ReOsub(2)sup(.) radicals respectively. The lower intensity of the spectra observed by KReO 4 samples irradiation showed a higher radioresistance of the KReO 4 than that of NaReO 4 . A radiolitical scheme taking into account the paramagnetic centers formation was proposed. (author)

  8. Concentration of 188Re-Perrhenate for Therapeutic Radiopharmaceuticals

    International Nuclear Information System (INIS)

    Bokhari, T.H.; Hina, S.; Ahmad, M.; Iqbal, M.

    2013-01-01

    Summary: Rhenium-188 (T1/2=16.9h) has great potential for a variety of therapeutic applications, including radionuclide synovectomy, oncology and bone pain palliation. The radioactive concentration of 188Re is dependent upon the specific activity of 188W, which dictates the bed size of the alumina/gel column. Due to the high content of inactive tungsten in neutron irradiated WO3, large columns containing aluminum oxide or gel are needed to prepare to double neutron capture based 188W/188Re generators that results in large elution volumes containing relatively high188W contents and low concentrations of /sup 188/ ReO/sub 4/ This decrease in specific volume of 188ReO/sub 4/ places a limitation because a high radioactive concentration of 188ReO4 - is always needed for filling angioplasty balloons or other therapeutic radiopharmaceuticals like188Re -EHDP 188Re -EDTMP, 188Re - MAG3 and 188Re -DTPA. We report post elution concentration of 188ReO4 - using in- house prepared lead cation exchange and alumina columns. Using these columns high bolus volume (10 mL saline) of 188ReO4 - can conveniently be concentrated in 1 mL of physiological saline for therapeutic use. (author)

  9. Tungsten-188/carrier-free rhenium-188 perrhenic acid generator system

    International Nuclear Information System (INIS)

    Knapp, F.F. Jr.; Lisic, E.C.; Mirzadeh, S.; Callahan, A.P.

    1993-01-01

    A generator system for providing a carrier-free radioisotope in the form of an acid comprises a chromatography column in tandem fluid connection with an ion exchange column, the chromatography column containing a charge of a radioactive parent isotope. The chromatography column, charged with a parent isotope, is eluted with an alkali metal salt solution to generate the radioisotope in the form of an intermediate solution, which is passed through the ion-exchange column to convert the radioisotope to a carrier-free acid form

  10. Treatment with rhenium-188-perrhenate and iodine-131 of NIS-expressing mammary cancer in a mouse model remarkably inhibited tumor growth

    Energy Technology Data Exchange (ETDEWEB)

    Dadachova, Ekaterina [Department of Nuclear Medicine, Albert Einstein College of Medicine, Bronx, NY 10461 (United States)]. E-mail: edadacho@aecom.yu.edu; Nguyen, Andrew [Department of Microbiology and Immunology, Albert Einstein College of Medicine, Bronx, NY 10461 (United States); Lin, Elaine Y. [Department of Developmental and Molecular Biology, Albert Einstein College of Medicine, Bronx, NY 10461 (United States); Gnatovskiy, Leo [Department of Developmental and Molecular Biology, Albert Einstein College of Medicine, Bronx, NY 10461 (United States); Lu, Ping [Department of Nuclear Medicine, Albert Einstein College of Medicine, Bronx, NY 10461 (United States); Pollard, Jeffrey W. [Department of Developmental and Molecular Biology, Albert Einstein College of Medicine, Bronx, NY 10461 (United States)

    2005-10-01

    Introduction: Novel therapeutic modalities are needed for breast cancer patients in whom standard treatments are not effective. Mammary gland sodium/iodide symporter has been identified as a molecular target in breast cancers in humans and in some transgenic mouse models. We report the results of a therapy study with {sup 131}I{sup -} and {sup 188}ReO{sub 4} {sup -} of breast cancer in polyoma middle T oncoprotein (PyMT) transgenic mice endogenously expressing the Na{sup +}/I{sup -} symporter (NIS). Methods: PyMT mice (12-13 weeks old) with one palpable tumor of 0.5-0.8 cm in diameter were used. For the therapy studies, PyMT mice were (1) treated with two intraperitoneal injections of 1.5 mCi of {sup 188}ReO{sub 4} {sup -} 1 week apart, (2) pretreated for 1 week with 5 {mu}g of triiodothyronine (T3) followed by two intraperitoneal injections of 1.5 mCi of {sup 131}I{sup -} 1 week apart or (3) left untreated. The tumor and normal organ uptakes were assessed by scintigraphic imaging. The thyroid function of treated and control animals was evaluated at the completion of the study by measuring the T3/thyroxine (T4) ratio in their blood. Results: There was significant uptake of {sup 131}I{sup -} and {sup 188}ReO{sub 4} {sup -} in the primary palpable tumors as well as in nonpalpable tumors, stomachs and thyroids. The tumor uptake after the second injection was 10 times lower in comparison with the first injection. Tumor growth was significantly inhibited in both the {sup 131}I{sup -} and {sup 188}ReO{sub 4} {sup -} groups in comparison with the control group, and tumors in the {sup 188}ReO{sub 4} {sup -} group increased in size significantly less than in the {sup 131}I{sup -} group. The T3/T4 ratios were calculated to be 27 and 25 for the control group and the {sup 188}ReO{sub 4} {sup -} group, respectively; for {sup 131}I{sup -}, both the T3 and T4 levels were below detection limit, demonstrating much less effect on the thyroids of treatment with {sup 188}ReO{sub 4} {sup -} than with {sup 131}I{sup -}. Conclusions: These results prove that NIS expression in breast tumors in animal models allows specific, efficient and safe treatment with a variety of radionuclides transported by NIS.

  11. Treatment with rhenium-188-perrhenate and iodine-131 of NIS-expressing mammary cancer in a mouse model remarkably inhibited tumor growth

    International Nuclear Information System (INIS)

    Dadachova, Ekaterina; Nguyen, Andrew; Lin, Elaine Y.; Gnatovskiy, Leo; Lu, Ping; Pollard, Jeffrey W.

    2005-01-01

    Introduction: Novel therapeutic modalities are needed for breast cancer patients in whom standard treatments are not effective. Mammary gland sodium/iodide symporter has been identified as a molecular target in breast cancers in humans and in some transgenic mouse models. We report the results of a therapy study with 131 I - and 188 ReO 4 - of breast cancer in polyoma middle T oncoprotein (PyMT) transgenic mice endogenously expressing the Na + /I - symporter (NIS). Methods: PyMT mice (12-13 weeks old) with one palpable tumor of 0.5-0.8 cm in diameter were used. For the therapy studies, PyMT mice were (1) treated with two intraperitoneal injections of 1.5 mCi of 188 ReO 4 - 1 week apart, (2) pretreated for 1 week with 5 μg of triiodothyronine (T3) followed by two intraperitoneal injections of 1.5 mCi of 131 I - 1 week apart or (3) left untreated. The tumor and normal organ uptakes were assessed by scintigraphic imaging. The thyroid function of treated and control animals was evaluated at the completion of the study by measuring the T3/thyroxine (T4) ratio in their blood. Results: There was significant uptake of 131 I - and 188 ReO 4 - in the primary palpable tumors as well as in nonpalpable tumors, stomachs and thyroids. The tumor uptake after the second injection was 10 times lower in comparison with the first injection. Tumor growth was significantly inhibited in both the 131 I - and 188 ReO 4 - groups in comparison with the control group, and tumors in the 188 ReO 4 - group increased in size significantly less than in the 131 I - group. The T3/T4 ratios were calculated to be 27 and 25 for the control group and the 188 ReO 4 - group, respectively; for 131 I - , both the T3 and T4 levels were below detection limit, demonstrating much less effect on the thyroids of treatment with 188 ReO 4 - than with 131 I - . Conclusions: These results prove that NIS expression in breast tumors in animal models allows specific, efficient and safe treatment with a variety of radionuclides transported by NIS

  12. Copper(II) perrhenate Cu(C{sub 3}H{sub 7}OH){sub 2}(ReO{sub 4}){sub 2}: Synthesis from isopropanol and CuReO{sub 4}, structure and properties

    Energy Technology Data Exchange (ETDEWEB)

    Mikhailova, D., E-mail: d.mikhailova@ifw-dresden.de [Karlsruhe Institute of Technology (KIT), Institute for Applied Materials (IAM), Hermann-von-Helmholtz-Platz 1, D-76434 Eggenstein-Leopoldshafen (Germany); Institute for Complex Materials, IFW Dresden, Helmholtzstrasse 20, D-01069 Dresden (Germany); Max Planck Institute for Chemical Physics of Solids, Nöthnitzer Str. 40, D-01187 Dresden (Germany); Engel, J.M. [Materials Science, Technische Universität Darmstadt, Alarich-Weiss-Str. 2, D-64287 Darmstadt (Germany); Schmidt, M. [Max Planck Institute for Chemical Physics of Solids, Nöthnitzer Str. 40, D-01187 Dresden (Germany); Tsirlin, A.A. [National Institute of Chemical Physics and Biophysics, Akadeemia tee 23, 12618 Tallinn (Estonia); Ehrenberg, H. [Karlsruhe Institute of Technology (KIT), Institute for Applied Materials (IAM), Hermann-von-Helmholtz-Platz 1, D-76434 Eggenstein-Leopoldshafen (Germany); Materials Science, Technische Universität Darmstadt, Alarich-Weiss-Str. 2, D-64287 Darmstadt (Germany)

    2015-12-15

    The crystal structure of Cu{sup +}Re{sup 7+}O{sub 4} is capable of a quasi-reversible incorporation of C{sub 3}H{sub 7}OH molecules. A room-temperature reaction between CuReO{sub 4} and C{sub 3}H{sub 7}OH under oxidizing conditions leads to the formation of a novel metal-organic hybrid compound Cu{sup 2+}(C{sub 3}H{sub 7}OH){sub 2}(ReO{sub 4}){sub 2}. Upon heating under reducing conditions, this compound transforms back into CuReO{sub 4}, albeit with ReO{sub 2} and metallic Cu as by-products. The crystal structure of Cu(C{sub 3}H{sub 7}OH){sub 2}(ReO{sub 4}){sub 2} solved from single-crystal X-ray diffraction (Pbca, a=10.005(3) Å, b=7.833(2) Å, and c=19.180(5) Å) reveals layers of corner-sharing CuO{sub 6}-octahedra and ReO{sub 4}-tetrahedra, whereas isopropyl groups are attached to both sides of these layers, thus providing additional connections within the layers through hydrogen bonds. Cu(C{sub 3}H{sub 7}OH){sub 2}(ReO{sub 4}){sub 2} is paramagnetic down to 4 K because the spatial arrangement of the Cu{sup 2+} half-filled orbitals prevents magnetic superexchange. The paramagnetic effective moment of 2.0(1) μ{sub B} is slightly above the spin-only value and typical for Cu{sup 2+} ions. - Highlights: • Novel Cu(C{sub 3}H{sub 7}OH){sub 2}(ReO{sub 4}){sub 2} compound has a sequence of inorganic and organic layers. • Hydrogen bonds provide an additional bonding Isopropanol molecules serve as a reducing agent during decomposition. • No direct Cu-O-Re-O-Cu connections via d{sub x2-y2} orbital of Cu{sup 2+} explain paramagnetism. • Hydrogen bonds provide an additional bonding. • Isopropanol molecules serve as a reducing agent during decomposition.

  13. Experimental Ion Exchange Column With SuperLig 639 And Simulant Formulation

    Energy Technology Data Exchange (ETDEWEB)

    Morse, Megan; Nash, C.

    2013-08-26

    SuperLig®639 ion exchange resin was tested as a retrieval mechanism for pertechnetate, through decontamination of a perrhenate spiked 5M Simple Average Na{sup +} Mass Based Simulant. Testing included batch contacts and a three-column ion exchange campaign. A decontamination of perrhenate exceeding 99% from the liquid feed was demonstrated. Analysis of the first formulation of a SBS/WESP simulant found unexpectedly low concentrations of soluble aluminum. Follow-on work will complete the formulation.

  14. Binding of ReO4- with an engineered MoO42--binding protein: towards a new approach in radiopharmaceutical applications

    International Nuclear Information System (INIS)

    Aryal, Baikuntha P.; Brugarolas, Pedro; He, Chuan

    2012-01-01

    Radiolabeled biomolecules are routinely used for clinical diagnostics. 99m Tc is the most commonly used radioactive tracer in radiopharmaceuticals. 188 Re and 186 Re are also commonly used as radioactive tracers in medicine. However, currently available methods for radiolabeling are lengthy and involve several steps in bioconjugation processes. In this work we present a strategy to engineer proteins that may selectively recognize the perrhenate (ReO 4 - ) ion as a new way to label proteins. We found that a molybdate (MoO 4 2- )-binding protein (ModA) from Escherichia coli can bind perrhenate with high affinity. Using fluorescence and isothermal titration calorimetry measurements, we determined the dissociation constant of ModA for ReO 4 - to be 541 nM and we solved a crystal structure of ModA with a bound ReO 4 - . On the basis of the structure we created a mutant protein containing a disulfide linkage, which exhibited increased affinity for perrhenate (K d = 104 nM). High-resolution crystal structures of ModA (1.7 (angstrom)) and A11C/R153C mutant (2.0 (angstrom)) were solved with bound perrhenate. Both structures show that a perrhenate ion occupies the molybdate binding site using the same amino acid residues that are involved in molybdate binding. The overall structure of the perrhenate-bound ModA is unchanged compared with that of the molybdate-bound form. In the mutant protein, the bound perrhenate is further stabilized by the engineered disulfide bond.

  15. Binding of ReO[subscript 4];#8722; with an engineered MoO[subscript 4 superscript 2];#8722;-binding protein: towards a new approach in radiopharmaceutical applications

    Energy Technology Data Exchange (ETDEWEB)

    Aryal, Baikuntha P.; Brugarolas, Pedro; He, Chuan (UC)

    2012-05-25

    Radiolabeled biomolecules are routinely used for clinical diagnostics. {sup 99m}Tc is the most commonly used radioactive tracer in radiopharmaceuticals. {sup 188}Re and {sup 186}Re are also commonly used as radioactive tracers in medicine. However, currently available methods for radiolabeling are lengthy and involve several steps in bioconjugation processes. In this work we present a strategy to engineer proteins that may selectively recognize the perrhenate (ReO{sub 4}{sup -}) ion as a new way to label proteins. We found that a molybdate (MoO{sub 4}{sup 2-})-binding protein (ModA) from Escherichia coli can bind perrhenate with high affinity. Using fluorescence and isothermal titration calorimetry measurements, we determined the dissociation constant of ModA for ReO{sub 4}{sup -} to be 541 nM and we solved a crystal structure of ModA with a bound ReO{sub 4}{sup -}. On the basis of the structure we created a mutant protein containing a disulfide linkage, which exhibited increased affinity for perrhenate (K{sub d} = 104 nM). High-resolution crystal structures of ModA (1.7 {angstrom}) and A11C/R153C mutant (2.0 {angstrom}) were solved with bound perrhenate. Both structures show that a perrhenate ion occupies the molybdate binding site using the same amino acid residues that are involved in molybdate binding. The overall structure of the perrhenate-bound ModA is unchanged compared with that of the molybdate-bound form. In the mutant protein, the bound perrhenate is further stabilized by the engineered disulfide bond.

  16. Binding of ReO4(-) with an engineered MoO4(2-)-binding protein: towards a new approach in radiopharmaceutical applications.

    Science.gov (United States)

    Aryal, Baikuntha P; Brugarolas, Pedro; He, Chuan

    2012-01-01

    Radiolabeled biomolecules are routinely used for clinical diagnostics. (99m)Tc is the most commonly used radioactive tracer in radiopharmaceuticals. (188)Re and (186)Re are also commonly used as radioactive tracers in medicine. However, currently available methods for radiolabeling are lengthy and involve several steps in bioconjugation processes. In this work we present a strategy to engineer proteins that may selectively recognize the perrhenate (ReO(4)(-)) ion as a new way to label proteins. We found that a molybdate (MoO(4)(2-))-binding protein (ModA) from Escherichia coli can bind perrhenate with high affinity. Using fluorescence and isothermal titration calorimetry measurements, we determined the dissociation constant of ModA for ReO(4)(-) to be 541 nM and we solved a crystal structure of ModA with a bound ReO(4)(-). On the basis of the structure we created a mutant protein containing a disulfide linkage, which exhibited increased affinity for perrhenate (K(d) = 104 nM). High-resolution crystal structures of ModA (1.7 Å) and A11C/R153C mutant (2.0 Å) were solved with bound perrhenate. Both structures show that a perrhenate ion occupies the molybdate binding site using the same amino acid residues that are involved in molybdate binding. The overall structure of the perrhenate-bound ModA is unchanged compared with that of the molybdate-bound form. In the mutant protein, the bound perrhenate is further stabilized by the engineered disulfide bond. © SBIC 2011

  17. On rhenium (7) state in aqueous solutions

    International Nuclear Information System (INIS)

    Sinyakova, G.S.

    1979-01-01

    The methods of spectrophotometry, electric conductivity and potentiometric titration have been used in studying the interaction in the system Re(7)-H 3 O + -H 2 O. It has been found that sodium perrhenate and perrhenic acid dissociate on dilution but not the way typical of binary electrolytes. Perrhenic acid is a mixture of the acids HReO 4 and H 5 ReO 6 . The two acids do not undergo differential titration. The conventional ionization constant, as calculated from the data of potentiometric titration, K 1 =(2.34+-0.52)x10 -2 . A step-wise dissociation of the H 4 ReO 6 - anion has been found, K 2 =(2.04+-0.30)x10 -8 , K 3 =(4.90+-0.20)x10 -12

  18. Removal of Pertechnetate-Related Oxyanions from Solution Using Functionalized Hierarchical Porous Frameworks

    Energy Technology Data Exchange (ETDEWEB)

    Banerjee, Debasis [Physical and Computational Science Directorate, Pacific Northwest National Laboratory, Richland WA 99352 USA; Elsaidi, Sameh K. [Physical and Computational Science Directorate, Pacific Northwest National Laboratory, Richland WA 99352 USA; Chemistry Department, Faculty of Science, Alexandria University, P.O. Box 426, Ibrahimia Alexandria 21321 Egypt; Aguila, Briana [Department of Chemistry, University of South Florida, USA; Li, Baiyan [Department of Chemistry, University of South Florida, USA; Kim, Dongsang [Energy and Environment Directorate, Pacific Northwest National Laboratory, Richland WA 99354 USA; Schweiger, Michael J. [Energy and Environment Directorate, Pacific Northwest National Laboratory, Richland WA 99354 USA; Kruger, Albert A. [US Department of Energy, Office of River Protection, Richland WA 99352 USA; Doonan, Christian J. [Department of Chemistry, The University of Adelaide, Adelaide South Australia 5005 Australia; Ma, Shengqian [Department of Chemistry, University of South Florida, USA; Thallapally, Praveen K. [Physical and Computational Science Directorate, Pacific Northwest National Laboratory, Richland WA 99352 USA

    2016-10-20

    Efficient and cost-effective removal of radioactive pertechnetate anions from nuclear waste is a key challenge to mitigate long-term nuclear waste storage issues. Traditional materials such as resins and layered double hydroxides (LDHs) were evaluated for their pertechnetate or perrhenate (the non-radioactive surrogate) removal capacity, but there is room for improvement in terms of capacity, selectivity and kinetics. A series of functionalized hierarchical porous frameworks were evaluated for their perrhenate removal capacity in the presence of other competing anions.

  19. High dilution calorimetric determination of the standard state thermodynamic differences between the properties of H+(aq) and Na+(aq) up to 598.15 K

    International Nuclear Information System (INIS)

    Djamali, Essmaiil; Cobble, James W.

    2009-01-01

    Standard state thermodynamic properties for fully ionized aqueous perrhenic acid at temperature in the range of (298.15 to 598.15) K and at p sat were determined by high dilution solution calorimetry (10 -4 m). A comparison of the standard state thermodynamic properties for fully ionized aqueous perrhenic acid, HReO 4 (aq), and sodium perrhenate, NaReO 4 (aq), establishes for the first time the quantitative values for the differences between H + (aq) and Na + (aq) from temperature of (298.15 to 598.15) K. Perrhenic acid is believed to be the first strong acid to be thermodynamically well characterized under standard state conditions to date from measurements down to 10 -4 m. The value of the Debye-Hueckel limiting slope for enthalpies of dilution at temperature of 596.30 K of 122 ± 6 kJ . mol -3/2 . kg 1/2 , obtained from the integral heats of solution measurement at various concentrations, is in good agreement with theoretical value in literature, 121 kJ . mol -3/2 . kg 1/2 . This agreement verifies that HReO 4 (aq) obeys the simple limiting law for strong electrolytes. Many thermodynamic properties of soluble sodium electrolytes can now be converted to the corresponding acid form.

  20. Sorption of technetium and its analogue rhenium on bentonite material under aerobic conditions

    International Nuclear Information System (INIS)

    Koudelkova, M.; Vinsova, H.; Konirova, R.; Ernestova, M.; Jedinakova-Krizova, V.; Tereesha, M.

    2003-01-01

    The uptake of technetium on bentonite materials has been studied from the point of view of characterization of long-term radioactive elements behavior in nuclear waste repository. Bentonite R (locality Rokle, Czech Republic) and two types of model groundwater (granitic and bentonite) were selected for the sorption experiments. The aim of our research has been to find out the conditions suitable for the technetium sorption on selected bentonite under oxidizing condition. The sorption experiments with Tc-99 on bentonite have been carried out by batch method. The influence of the addition of different materials (e.g. activated carbon, graphite, Fe 2+ ) with bentonite, the effect of solid: aqueous phase ratio and a pH value on the percentage of technetium uptake and on the K d values were tested. Perrhenate was selected as an analogue of pertechnetate in non-active experiments of capillary electrophoresis (CE) and isotachophoresis (ITP). The percentage of rhenium sorbed on bentonite material was determined from the decrease of perrhenate peak area (CE) and from the shortening of the ITP zone corresponding to perrhenate. Both electromigration methods provided comparable results. The results obtained in this study with non-active material were compared to those of technetium acquired by radiometry and polarography. The 8 days kinetics of the perrhenate and pertechnetate sorption on bentonite was described mathematically with a tendency to predict long-term behavior of studied systems. (authors)

  1. Influence of the acid and basic properties of rhenium oxide supported on alumina catalyst on the catalytic performance in olefin metathesis; Influence des proprietes acido-basiques de l`oxyde de rhenium supporte sur les performances catalytiques en metathese des olefines

    Energy Technology Data Exchange (ETDEWEB)

    Nahama, F.

    1996-11-30

    The aim of this work is to study the influence of the acid-basic properties of rhenium oxide supported on alumina catalyst on the catalytic performance in olefin metathesis. The literature data indicate that the environment of the active site does possess acid properties. However, the nature of the acid sites is still matter of debate. Concerning the Re O{sub x} - Al{sub 2}O{sub 3} interactions, we have shown that perrhenate ions are electrostatically absorbed on alumina. The uptake of rhenium is favoured at acidic pH (below 4), and the absorbed rhenium is in equilibrium with rhenium in solution. The results of rhenium extraction by water strongly suggest that the surface compounds of the calcined Re{sub 2}O{sub 7}/Al{sub 2}O{sub 3} materials is aluminium perrhenate. Characterization of surface acidity of the catalyst by infrared spectroscopy reveals that the initiation of the metathesis reaction is governed essentially by Lewis acidity. This strongly supports the role of Lewis acidity, which is exalted by the increase of the rhenium content and the calcination temperature. Finally, we point out by ammonia adsorption-thermodesorption a band at 1320 cm{sup -1} characteristic of the Lewis acidity of aluminium perrhenate. This result is a second indication of the presence of aluminium perrhenate on the Re{sub 2}O{sub 7}/Al{sub 2}O{sub 3} catalyst surface. (author)

  2. Labelled biomolecules with Sm-153, Re-188 and Y-90 for targeted radiotherapy

    International Nuclear Information System (INIS)

    Ahmad, M.; Pervez, S.

    2000-01-01

    Direct labeling of Lanreotide with Rhenium-188 was studied. Reduction of cysteine bridge was performed by reducing agents (ascorbic acid, 2ME). The perrhenate eluted from the generator was reduced with stannous chloride. Tartarate was used as transchelating agent. After pH adjustment, shaking and incubation for various time intervals were carried out. Thin Layer chromatography and reverse phase chromatography were used to monitor the radiolabelling yield. Stability of radiolabelled Lanreotide was also checked

  3. Labelled biomolecules with SM-153, Re-188 and Y-90 for targeted radiotherapy. Pakistan

    International Nuclear Information System (INIS)

    Ahmad, Mushtaq; Pervez, Shahid

    2000-01-01

    Direct labeling of Lanreotide with Rhenium-188 was studied. Reduction of cysteine bridge was performed by reducing agents (ascorbic acid, 2ME). The perrhenate eluted from the generator was reduced with stannous chloride. Tartarate was used as transchelating agent. After pH adjustment, shaking and incubation for various time intervals were carried out. Thin layer chromatography and reverse phase chromatography were used to monitor the radiolabelling yield. Stability of radiolabelled Lanreotide was also checked

  4. ELECTROCHEMICAL STUDY OF RHENIUM-TELLURIUM-COPPER SYSTEM

    OpenAIRE

    E.A.Salakhova*1, D.B.Tagiyev2, P.E.Kalantarova3 and A.M.Askerova4

    2017-01-01

    The formation of the triple alloys Re-Te-Cu on the platinum electrode at volt amperemetric cycling has been studied. The investigation was carried out from chloride acidic solution containing tellurium acid, potassium perrhenate, chloride copper. The kinetics of the processes was controlled using the measurements by the method of cyclic volt-amperometry on the device İVİUMSTAT. For the analysis of composition and structure the methods of XRD (X-ray diffraction analysis) were used, and the inv...

  5. Affinity of hydroxyapatite by radionuclides parent/child in 188Re/188W generator for radiotherapy

    International Nuclear Information System (INIS)

    Carrera D, A. A.; Badillo A, V.; Badillo A, V. E.; Monroy G, F.

    2009-10-01

    To assess the feasibility of using apatites as matrices of 188 W/ 188 Re generator is essential to obtain the distribution coefficients as much of parent radionuclide as child radionuclide in apatite, that is to say to know their affinity for the solid. It was selected the mineral species more representative as adsorbent, the hydroxyapatite Ca 10 (PO 4 ) 6 (OH) 2 it is known for its great capacity of ions retention and by presenting a large affinity for anionic species in their surface. In this paper we use a synthetic hydroxyapatite marketed by Bio-Rad. This paper presents the preliminary results regarding the affinity of hydroxyapatite for the anionic species tungstates (WO 4 2- ) and perrhenates (ReO 4 - in EDTA, as background electrolyte expressed as distribution coefficients between two immiscible phases obtained with the help of radioactive tracers 187 W and 188 Re respectively. The retention measures of these ions, traces show that Bio-Gel hydroxyapatite presents moderate values of distribution coefficients for anionic species of W(Vi) in EDTA 0.01 mol/L that are in the range p H 5 to 6.5; the parent radionuclide of generator 188 Re/ 188 W is fixed but not enough to consider it a good absorbent. By contrast, the fixation of perrhenate ions is virtually wiped as may be easily removed from a hydroxyapatite column packed with a saline solution. The influence of this saline solution in the removal of perrhenate ions is null practically. (Author)

  6. Rhenium-188 as an alternative to Iodine-131 for treatment of breast tumors expressing the sodium/iodide symporter (NIS)

    International Nuclear Information System (INIS)

    Dadachova, E.; Bouzahzah, B.; Zuckier, L.S.; Pestell, R.G.

    2002-01-01

    The sodium-iodide symporter (NIS), which transports iodine into the cell, is expressed in thyroid tissue and was recently found to be expressed in approximately 80% of human breast cancers but not in healthy breast tissue. These findings raised the possibility that therapeutics targeting uptake by NIS may be used for breast cancer treatment. To increase the efficacy of such therapy it would be ideal to identify a radioactive therapy with enhanced local emission. The feasibility of using the powerful beta-emitting radiometal 188 Re in the form of 188 Re-perrhenate was therefore compared with 131 I for treatment of NIS-expressing mammary tumors. In the current studies, using a xenografted breast cancer model induced by the ErbB2 oncogene in nude mice, 188 Re-perrhenate exhibited NIS-dependent uptake into the mammary tumor. Dosimetry calculations in the mammary tumor demonstrate that 188 Re-perrhenate is able to deliver a dose 4.5 times higher than 131 I suggesting it may provide enhanced therapeutic efficacy

  7. Affinity of hydroxyapatite by radionuclides parent/child in {sup 188}Re/{sup 188}W generator for radiotherapy; Afinidad de la hidroxiapatita por los radionuclidos padre/hijo en el generador {sup 188}Re/{sup 188}W para radioterapia

    Energy Technology Data Exchange (ETDEWEB)

    Carrera D, A. A. [Universidad Autonoma de Zacatecas, Unidad Academica de Ciencias Quimicas, Campus Universitario Siglo XXI, Ejido La Escondida, Carretera a Guadalajara Km. 6 (Mexico); Badillo A, V. [Universidad Autonoma de Zacatecas, Unidad Academica de Estudios Nucleares, Calle Cipres No. 10, Fracc. La Penuela 98068, Zacatecas (Mexico); Badillo A, V. E.; Monroy G, F. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)], e-mail: ana_carrera7@hotmail.com

    2009-10-15

    To assess the feasibility of using apatites as matrices of {sup 188}W/{sup 188}Re generator is essential to obtain the distribution coefficients as much of parent radionuclide as child radionuclide in apatite, that is to say to know their affinity for the solid. It was selected the mineral species more representative as adsorbent, the hydroxyapatite Ca{sub 10} (PO{sub 4}){sub 6}(OH){sub 2} it is known for its great capacity of ions retention and by presenting a large affinity for anionic species in their surface. In this paper we use a synthetic hydroxyapatite marketed by Bio-Rad. This paper presents the preliminary results regarding the affinity of hydroxyapatite for the anionic species tungstates (WO{sub 4}{sup 2-}) and perrhenates (ReO{sub 4}{sup -} in EDTA, as background electrolyte expressed as distribution coefficients between two immiscible phases obtained with the help of radioactive tracers {sup 187}W and {sup 188}Re respectively. The retention measures of these ions, traces show that Bio-Gel hydroxyapatite presents moderate values of distribution coefficients for anionic species of W(Vi) in EDTA 0.01 mol/L that are in the range p H 5 to 6.5; the parent radionuclide of generator {sup 188}Re/{sup 188}W is fixed but not enough to consider it a good absorbent. By contrast, the fixation of perrhenate ions is virtually wiped as may be easily removed from a hydroxyapatite column packed with a saline solution. The influence of this saline solution in the removal of perrhenate ions is null practically. (Author)

  8. Sorption of technetium and its analogue rhenium on bentonite material under aerobic conditions

    International Nuclear Information System (INIS)

    Vinsova, H.; Koudelkova, M.; Konirova, R.; Vecernik, P.; Jedinakova-Krizova, V.

    2003-01-01

    The uptake of technetium on bentonite materials has been studied from the point of view of characterization of long-term radioactive elements behavior in nuclear waste repository. Bentonite R (locality Rokle, Czech Republic) and two types of model groundwater (granitic and bentonite) were selected for the sorption experiments. It is generally known that bentonite materials show an excellent cation-exchange capacity and, on the other hand, a poor uptake of anions. Technetium occurs under aerobic conditions in its most stable oxidation state (+VII) as pertechnetate, which makes a question of its sorption on bentonite more complex when compared with e.g. Cs + or Sr 2+ . To increase the K d values for technetium sorption on bentonite, it is necessary to carry out the experiments under anaerobic conditions in the presence of reducing agent, which is capable to lower the oxidation state of technetium which enables its successful immobilization. The aim of our research has been to find out the conditions suitable for the technetium sorption on selected bentonite under oxidizing conditions. The sorption experiments with Tc-99 on bentonite have been carried out by batch method. The influence of the addition of different materials (e.g. activated carbon, graphite, Fe 2+ , Fe) with bentonite, the effect of solid:aqueous phase ratio and a pH value on the percentage of technetium uptake and on the K d values were tested. Perrhenate was selected as an analogue of pertechnetate in non-active experiments of capillary electrophoresis (CE) and isotachophoresis (ITP). The percentage of rhenium sorbed on bentonite material was determined from the decrease of perrhenate peak area (CE) and from the shortening of the ITP zone corresponding to perrhenate. Both electromigration methods provided comparable results. The results obtained in this study with non-active material were compared to those of technetium acquired by radiometry and polarography. (authors)

  9. Stability of rhenium-188 labeled antibody

    International Nuclear Information System (INIS)

    Lim, B. K.; Jung, J. M.; Jung, J. K.; Lee, D. S.; Lee, M. C.

    1999-01-01

    For clinical application of beta-emitter labeled antibody, high specific activity is important. Carrier-free Re-188 from W-188/Re-188 generator is an ideal radionuclide for this purpose. However, low stability of Re-188 labeled antibody, especially in high specific activity, due to radiolytic decomposition by high energy (2.1 MeV) beta ray was problem. We studied the stability of Re-188 labeled antibody, and stabilizing effect of several nontoxic radical-quenching agents. Pre-reduced monoclonal antibody (CEA79.4) was labeled with Re-188 by incubating with generator-eluted Re-188-perrhenate in the presence of stannous tartrate for 2 hr at room temperature. Radiochemical purity of each preparation was determined by chromatography (ITLC-SG/acetone, ITLC-SG/Umezawa, Whatman No.1/saline). Human serum albumin was added to the labeled antibodies(2%). Stability of Re-188-CEA79.4 was investigated in the presence of vitamin C, ethanol, or Tween 80 as radical-quenching agents. Specific activities of 4.29∼5.11 MBq/μg were obtained. Labeling efficiencies were 88±4%(n=12). Very low stability after removal of stannous tartrate from the preparation was observed. If stored after purging with N 2 , all the preparations were stable for 10 hr. However, if contacted with air, stability decreased. Perrhenate and Re-188-tartrate was major impurity in declined preparation (12∼47 and 9∼38% each, after 10 hr). Colloid-formation was not a significant problem in all cases. Addition of vitamin C stabilized the labeled antibodies either under N 2 or under air by reducing the formation of perrhenate. High specific activity Re-188 labeled antibody is unstable, especially, in the presence of oxygen. Addition of vitamin C increased the stability

  10. A comparative study of electrochemical and optical properties of rhenium deposited on gold and platinum

    Energy Technology Data Exchange (ETDEWEB)

    Zerbino, Jorge O.; Castro Luna, Ana M.; Martins, M. E. [Consejo Nacional de Investigaciones Cientificas y Tecnicas (CONICET), Buenos Aires (Argentina). Inst. de Investigaciones Fisico-Quimicas, Teoricas y Aplicadas (INIFTA)]. E-mail: mmartins@inifta.unlp.edu.ar; Zinola, Carlos F.; Mendez, Eduardo [Universidad de la Republica, Montevideo (Uruguay). Facultad de Ciencias. Lab. de Electroquimica Fundamental

    2002-08-01

    Rhenium-containing films were grown on gold and platinum after different potentiostatic and potentiodynamic polarizations in the - 0.20 V to 0.70 V range (vs rhe) in aqueous acid perrhenate. Experimental data were obtained using cyclic voltammetry and ellipsometry, from which the thickness and optical indices of the electrodeposited rhenium layer were calculated. Metallic rhenium deposition on gold takes place at potentials within the hydrogen evolution reaction. Rhenium oxide on platinum is formed in the hydrogen adatom potential domain, whereas metallic rhenium is deposited concurrently with the hydrogen adsorption and evolution reactions on the same metal. (author)

  11. A comparative study of electrochemical and optical properties of rhenium deposited on gold and platinum

    Directory of Open Access Journals (Sweden)

    Zerbino Jorge O.

    2002-01-01

    Full Text Available Rhenium-containing films were grown on gold and platinum after different potentiostatic and potentiodynamic polarizations in the - 0.20 V to 0.70 V range (vs rhe in aqueous acid perrhenate. Experimental data were obtained using cyclic voltammetry and ellipsometry, from which the thickness and optical indices of the electrodeposited rhenium layer were calculated. Metallic rhenium deposition on gold takes place at potentials within the hydrogen evolution reaction. Rhenium oxide on platinum is formed in the hydrogen adatom potential domain, whereas metallic rhenium is deposited concurrently with the hydrogen adsorption and evolution reactions on the same metal.

  12. Cermets based on rhenium and rare earth element oxides

    International Nuclear Information System (INIS)

    Varfolomeev, M.B.; Velichko, A.V.; Zajtseva, L.L.; Shishkov, N.V.

    1977-01-01

    The reduction of perrhenates of rare earth elements and of yttrium by hydrogen and the subsequent sintering have yielded cermets based on rhenium and rare earth element oxides inherent in which are more disperse and homogeneous structures than those of the ''molecular'' rare earth element-Tc cermets. The dispersity of cermets increases in the rare earth elements series from La to Lu. The microhardness of the Re phase in cermets is 490 kgf/mm 2 ; the total microhardness of a cermet is substantially higher

  13. Applications of precision colorimetry to elemental microanalysis

    International Nuclear Information System (INIS)

    Debal, E.; Peynot, S.; Poliakoff, O.; Revault, M.

    1979-01-01

    The sample (< 1 mg) is burnt in an oxygen flask for the determination of rhenium. It is destroyed by a wet process in a Kjeldahl flask for the determination of rhodium or tellurium (sample < 4 to 5 mg) or zirconium (sample < 1.5 mg). These elements are determined spectrophotometrically. The following reactions are used: reduction of perrhenate by tin(II) chloride in the presence of 2,2'-furildioxime or thiourea, complexation of rhodium(III) by sodium hypochlorite, formation of iodotellurite, complexation of zirconium(IV) with Xylenol Orange. (author)

  14. Osmotic and activity coefficients of aqueous NaTcO4 and NaReO4 solutions at 250C

    International Nuclear Information System (INIS)

    Boyd, G.E.

    1978-01-01

    Isopiestic vapor-pressure comparison experiments were performed with aqueous binary sodium perchlorate, pertechnetate, and perrhenate solutions to concentrations of approximately 8.5 m. Osmotic coefficients for these solutions and mean molal ionic activity coefficients for NaTcO 4 and NaReO 4 were derived from the isotonic molalities. Pitzer's treatment was applied to describe the concentration dependence of the osmotic coefficients of NaClO 4 , NaTcO 4 , and NaReO 4 , and the implications of the parameters derived from a least-squares fit are discussed in terms of solvent structure and interionic forces. 4 tables, 1 figure

  15. Ion Exchange Column Tests Supporting Technetium Removal Resin Maturation

    Energy Technology Data Exchange (ETDEWEB)

    Nash, C. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McCabe, D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Hamm, L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Smith, F. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Morse, M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2013-12-20

    The primary treatment of the tank waste at the DOE Hanford site will be done in the Waste Treatment and Immobilization Plant, currently under construction. The baseline plan for this facility is to treat the waste, splitting it into High Level Waste (HLW) and Low Activity Waste (LAW). Both waste streams are then separately vitrified as glass and sealed in canisters. The LAW glass will be disposed on site. There are currently no plans to treat the waste to remove technetium, so its disposition path is the LAW glass. Due to the soluble properties of pertechnetate and long half-life of 99Tc, effective management of 99Tc is important. Options are being explored to immobilize the supplemental LAW portion of the tank waste, as well as to examine the volatility of 99Tc during the vitrification process. Removal of 99Tc, followed by off-site disposal has potential to reduce treatment and disposal costs. A conceptual flow sheets for supplemental LAW treatment and disposal that could benefit from technetium removal will specifically examine removing 99Tc from the LAW feed stream to supplemental immobilization. SuperLig® 639 is an elutable ion exchange resin. In the tank waste, 99Tc is predominantly found in the tank supernate as pertechnetate (TcO4-). Perrhenate (ReO4-) has been shown to be a good non-radioactive surrogate for pertechnetate in laboratory testing for this ion exchange resin. This report contains results of experimental ion exchange distribution coefficient and column resin maturation kinetics testing using the resin SuperLig® 639a to selectively remove perrhenate from simulated LAW. This revision includes results from testing to determine effective resin operating temperature range. Loading tests were performed at 45°C, and the computer modeling was updated to include the temperature effects. Equilibrium contact testing indicated that this batch of

  16. Purification of alkaline solutions and wastes from actinides and technetium by coprecipitation with some carriers using the method of appearing reagents: Final Report

    International Nuclear Information System (INIS)

    Peretrukhin, V.F.; Silin, V.I.; Kareta, A.V.; Gelis, A.V.; Shilov, V.P.; German, K.E.; Firsova, E.V.; Maslennikov, A.G.; Trushina, V.E.

    1998-09-01

    The coprecipitation of transuranium elements (TRU) and technetium from alkaline solutions and from simulants of Hanford Site tank wastes has been studied in reducing and oxidizing conditions on uranium(IV,VI) hydroxocompounds, tetraalkylammonium perrhenate and perchlorate, and on hydroxides of Fe(III), Co(III), Mn(II), and Cr(III) using the method of appearing reagents (MAR). Coprecipitations in alkaline solution have been shown to give high decontamination factors (DF) at low content of carrier and in the presence of high salt concentrations. Uranium(IV) hydroxide in concentrations higher than 3 x 10 -3 M coprecipitates Pu and Cm in any oxidation state from 0.2 to 4 M NaOH with DFs of 110 to 1000 and Np and Tc with DFs of 51 to 176. Technetium (VII) coprecipitates with (5 to 8) x 10 -4 M tetrabutylammonium (TBA) perrhenate in 0.01 to 0.02 M TBA hydroxide from 0.5 to 1.5 M NaOH to give DFs of 150 to 200. Coprecipitations of Np and Pu with Co(OH) 3 , Fe(OH) 3 , Cr(OH) 3 , and Mn(OH) 2 obtained by the MAR from precursors in the range from pH 10.5 to 0.4 M NaOH give DFs from 80 to 400

  17. Comparison of carrier-added [99mTc] EDTMP and carrier-free preparations of [99mTc] EDTMP and [99mTc] DPD

    International Nuclear Information System (INIS)

    Krcal, A.; Kletter, K.; Dudczak, R.; Pirich, C.; Mitterhauser, M.

    2002-01-01

    Full text: High uptake of bone-seeking radiopharmaceuticals in malignant bone lesions is a prerequisite for adequate bone scanning. Visual image analysis is impaired due to high soft-tissue activity with currently available [ 99m Tc]-EDTMP-kits. This study aimed to compare carrier-added [ 99m Tc]-EDTMP with carrier-free [ 99m Tc]-EDTMP and [ 99m Tc]-DPD preparations in clinical routine. 15 μg and 150 μg perrhenic acid respectively were added to [ 99m Tc]-pertechnetate (>6 GBq in 3 ml phys. saline). The solution was then transferred into a vial, containing 1 mg of EDTMP, 3.6 mg stannous(II)chloride and 10 mg ascorbic acid under inert conditions. Under vigorous stirring the reaction mixture was heated to 45 o C for 10 min. After cooling down to room temperature the labelling mixture was sterile filtrated (millipore 0.22 μm). Quality control was performed using radio-ITLC (Whatman SG; acetone or ethanol: R f perrhenate/pertechnetate 0.87, colloid/product 0.05; phys. saline: R f colloid 0.00, perrhenate/pertechnetate and product 0.9) allowing rapid and efficient assessment of the product. Carrier free [ 99m Tc]-EDTMP and [ 99m Tc]-DPD were prepared according to instructions of the manufacturer. Clinical studies were performed in 29 patients according to a routine bone scanning protocol by injecting 700-800 MBq of the respective tracer and whole body imaging 3 h thereafter. Radiochemical purity and radiochemical yield relied on various parameters such as concentration of carrier and reducing agent and reaction conditions (pH, reaction time, temperature). Means of the labelling yield were 22 % for the preparation using 150 μg of carrier (5 preparations), 80 % for the preparation using 15 μpg of carrier (10 preparations) and 91 % for the carrier free products (5 preparations). Radiochemical purity was >96 % in all experiments. Colloid was formed in very low amounts, and was completely removed by sterile filtration. In clinical studies quantitative analysis

  18. Use of a new tandem cation/anion exchange system with clinical-scale generators provides high specific volume solutions of technetium-99m and rhenium-188

    International Nuclear Information System (INIS)

    Knapp, F.R. Jr.; Beets, A.L.; Mirzadeh, S.; Guhlke, S.; Univ. of Bonn

    1998-03-01

    In this paper the authors describe the first application of a simple and inexpensive post elution tandem cation-anion exchange column system which is based on generator elution with salts of weak acids such as ammonium acetate instead of saline solution to provide very high specific volume solutions of technetium-99m and rhenium-188 from clinical scale molybdenum-99/technetium-99m generator prepared from low specific activity (n,y) molybdenum-99, and tungsten-188/rhenium-188 generators, respectively. Initial passage of the bolus through a strong cation exchange cartridge converts the ammonium acetate to acetic acid which is essentially not ionized at the acidic pH, allowing specific subsequent amine type (QMA SepPak trademark) anion exchange cartridge column trapping of the microscopic levels of the pertechnetate or perrhenate. Subsequent elution of the anion cartridge with a small volume ( 500 mCi/mL) from the alumina-based tungsten-188/rhenium-188 generator

  19. Excited states of ReO4-: A comprehensive time-dependent relativistic density functional theory study

    Science.gov (United States)

    Xu, Wenhua; Ma, Jianyi; Peng, Daoling; Zou, Wenli; Liu, Wenjian; Staemmler, Volker

    2009-02-01

    The perrhenate anion, ReO4-, is taken as a showcase of heavy transition metal complexes, to examine the performance of time-dependent relativistic density functional linear response theory for electronic excitations, which is based on a newly proposed exact two-component Hamiltonian resulting from the symmetrized elimination of the small component. In total 30 scalar and 63 spinor excited states are investigated and the results are grossly in good agreement with those by the singles and doubles coupled-cluster linear response theory. It is found that only a few scalar states of 3T1 and 3T2 symmetries are split significantly by the spin-orbit coupling, whereas only those excited states involving the Rydberg-type virtual orbital are affected by the solvent effects. The nature of the optical absorption spectra is also highlighted.

  20. Excited states of ReO4-: A comprehensive time-dependent relativistic density functional theory study

    International Nuclear Information System (INIS)

    Xu Wenhua; Ma Jianyi; Peng Daoling; Zou Wenli; Liu Wenjian; Staemmler, Volker

    2009-01-01

    The perrhenate anion, ReO 4 - , is taken as a showcase of heavy transition metal complexes, to examine the performance of time-dependent relativistic density functional linear response theory for electronic excitations, which is based on a newly proposed exact two-component Hamiltonian resulting from the symmetrized elimination of the small component. In total 30 scalar and 63 spinor excited states are investigated and the results are grossly in good agreement with those by the singles and doubles coupled-cluster linear response theory. It is found that only a few scalar states of 3 T 1 and 3 T 2 symmetries are split significantly by the spin-orbit coupling, whereas only those excited states involving the Rydberg-type virtual orbital are affected by the solvent effects. The nature of the optical absorption spectra is also highlighted

  1. Dinuclear 1,4,7-triazacyclononane (tacn) complexes of cobalt(III) with amido and tacn bridges. Synthesis, characterization and reversible acid-accelerated bridge cleavage

    DEFF Research Database (Denmark)

    Andersen, Peter; Glerup, Jørgen; Gumm, Andreas

    2004-01-01

    -tacn(-H)]Co(NH3)]3+, were isolated as perchlorates, and the crystal structure of the perrhenate of the latter complex was determined by X-ray diffraction. In this compound a nitrogen atom (deprotonated) from one of the tacn ligands forms a third bridge together with two amido bridges. In 1.0 M (Na,H)ClO4 ([H+] 0......)]4+. An isolated perchlorate of this complex appeared to be the salt of the trans-ammineaqua isomer as determined by X-ray diffraction. Equilibration from both sides fits the first-order rate constant dependence k(obs)=6.2(3) x 10(-5)[H+] + 2.1(2) x 10(-5)(s(-1)) at 40 degrees C. Prolonged treatment of the two...

  2. Eichrom's ABEC trademark resins: Alkaline radioactive waste treatment, radiopharmaceutical, and potential hydrometallurgical applications

    International Nuclear Information System (INIS)

    Bond, A.H.; Gula, M.J.; Chang, F.; Rogers, R.D.

    1997-01-01

    Eichrom's ABEC trademark resins selectivity extract certain anions from high ionic strength acidic, neutral, or strongly alkaline media, and solute stripping can be accomplished by eluting with water. ABEC resins are stable to pH extreme and radiolysis and operate in high ionic strength and/or alkaline solutions where anion-exchange is often ineffective. Potential applications of the ABEC materials include heavy metal and ReO 4 - separations in hydrometallurgy and purification of perrhenate iodide, and iodate in radiopharmaceutical production. Separation of 99m TcO 4 - from its 99 MoO 4 2- parent and stripping with water or physiological saline solution have been demonstrated for radiopharmaceutical applications. Removal of 99 TcO 4 - and 129 I - from alkaline tank wastes has also been successfully demonstrated. The authors will discuss the scale-up studies, process-scale testing, and market development of this new extraction material

  3. Determination of radiochemical yields of 186Re-labelled complexes using thin layer chromatography

    International Nuclear Information System (INIS)

    Konirova, R.; Kohlickova, M.; Jedinakova-Krizova, V.

    1999-01-01

    The reaction conditions for synthesis of three rhenium complexes 186 Re-methylendiphosphonate (MDP), 186 Re-hydroxyethylidendiphosphonate (HEDP) and 186 Re-citrate have been investigated. Radiochemical yield of complexation has been determined by thin layer chromatography and paper chromatography. The rhenium complexation with corresponding ligand is dependent on pH values of reaction mixture, concentration of studied ligand (MDP, HEDP and sodium citrate) and concentration of reducing agent. Stannous chloride with ascorbic acid (as antioxidant) was used for reduction of perrhenate. The labeling yield of 186 Re-MDP was about 90 %, of 186 Re-HEDP more than 80 % and more than 75 % for 186 Re-citrate under optimum conditions. Besides, the possibility of application of porphyrins as organic ligands for complexation with rhenium isotopes is examined. (authors)

  4. Preparation of 188Re labelled antibodies

    International Nuclear Information System (INIS)

    Zhu Minghua; Cao Rongzhen; Li Wenxin; Sheng Rong; Yin Duanzhi; He Weiyu; Zhou Wei; Wang Yongxian

    1998-01-01

    A simple technique of directly labelling antibodies with 188 Re has been developed. The reduction of antibody disulfide groups was achieved by incubation of antibody with ascorbic acid (pH = 6.5) for an hour at room temperature and a solution of excess SnCl 2 in sodium gluconate was added to the AA-reduced antibody followed by the addition of perrhenate. Some factors that influence labelling efficiency, such as the pH of the reaction mixture, the labelling time, and the amount of antibodies and reductive agent, were studied experimentally and a better labelling method was established. The labelling yields, as determined by paper chromatography, were greater than 80%

  5. Diffusion of 99-technetium in bentonite under aerobic and anaerobic conditions

    International Nuclear Information System (INIS)

    Vecernik, P.; Jedinakova-Krizova, V.; Vokal, A.

    2006-01-01

    Diffusion experiments were performed with 99 Tc and Re (a model of technetium) in the form of pertechnetate and perrhenate in bentonite from the Rokle locality (Czech Republic). The through diffusion method was used, and the apparent diffusion coefficients (D a ) were evaluated. The effects of the particle mesh-size, bulk densities, and aerobic or anaerobic conditions on the diffusion were studied in view of the fact that oxidizing or reducing conditions influence the chemical forms of technetium and rhenium. In the presence of oxygen, technetium and rhenium occur in oxidation state VII, as anions which are soluble and mobile in the environment, whereas in reducing conditions they occur in lower oxidation states, mainly as insoluble oxides or hydroxides. Aerobic experiments were carried out in common laboratory conditions, anaerobic experiments were performed under nitrogen

  6. Production of carrier-free 188Re in the past ten years in Taiwan

    International Nuclear Information System (INIS)

    Bor-Tsung Hsieh; Institute of Nuclear Energy Research, Taiwan; Wan-Yu Lin; Tsai-Yueh Luo; Kai-Yuan Cheng

    2007-01-01

    Twenty clinical scale alumina-based 188 W/ 188 Re generators and carrier-free 188 Re has been produced at the Institute of Nuclear Energy Research (INER-Taiwan) for over ten years. 2845.6 GBq (76.9 Ci) of 188 Re-perrhenate solution has been eluted from generators during the past ten years. We have used the harvesting 188 Re solution for labeling radiopharmaceuticals, such as 188 Re-HEDP, 188 Re-MDP, 188 Re-microsphere, 188 Relipiodol, and 188 Re-sulfur colloid, etc. The average eluting yield of 188 Re is 78.6±5.8% that was investigated at 1115 harvesting times from 20 generators. Each generator can be used more than six months but the Millipore needs to be changed every two months for smooth harvesting and high yield of 188 Re solution. (author)

  7. Voltammetric assay of extremely low technetium concentrations following enrichment at the HMDE after reaction with Thiocyanate

    International Nuclear Information System (INIS)

    Friedrich, M.; Ruf, H.

    1984-12-01

    It is known that in sulfuric acid solution pertechnetate is reduced by thiocyanate to form thiocyanate complexes. After this reaction the technetium acquires the capability of being adsorbed at the hanging mercury drop electrode (HMDE) provided that a potential of -0,40 V (vs. Ag/AgCl) has been applied to the electrode. If, by application of the differential pulse voltammetry after the phase of deposition the potential at the electrode is scanned cathodically, traces of technetium can be determined very sensitively by evaluation of the peak current recorded at minus 1,27 V (Ag/AgCl). The effect is still being enhanced by the presence of not interfering small perrhenate amounts. The reproducibility of the measured values is excellent. (orig.) [de

  8. Electrodialysis separation of rhenium from silicon

    International Nuclear Information System (INIS)

    Prasolova, O.D.; Borisova, L.V.; Ermakov, A.N.

    1989-01-01

    A method of separation of ruthenium from silicon by electrodialysis with heterogenuos ion-exchange membranes is developed. The effeciency of purification of rhenium from silicon depending on the number of dialyzer chambers, temperature and pH value of the dialyzate is studed. It is found that an addditional fourth chamber between the middle and anolytic ones causes the purification coefficient increase 50 times. It is necessary to cool the dialyzate in order to reduce silicon migration into the anolyte and reverse diffusion of perrhenate-ion from the anolyte into the dialyzate. The optimal pH value of diaizate is 5.5-6. The method developed has been used for separating rhenium from industrial solution of lead production with complex composition

  9. Introduction to crystal structure determination methods using x-ray diffraction: application to some rare earth complexes

    International Nuclear Information System (INIS)

    Oliveira, M.A. de.

    1986-01-01

    This work is composed by a theoretical introduction studying crystal concept, interaction between X-ray and crystal medium, and methods for determining small molecular structures applied in solution of crystal structures of praseodymium, neodymium and europium complexes with perrhenate and trans - 1,4 - dithiane - 1,4 - dioxide, (TDTD), which general formula is [ Ln (H sub(2) O) sub(4) (η-TDTD) (η'Re O sub(4)) (μ-η sup(2)-TDTD)] sub(n) (Re O sub(4)) sub(2n). nTDTD, where, Ln = Eu, Pr, Nd and methyl-2,6-anhydrous-3-azido-4-0-benzoyl-3-deoxy-α-D-iodo pyranoside. The structure of C sub(14) H sub(15) N sub(3) O sub(5) organic complex was determined using direct methods. (M.C.K.)

  10. Effect of carrier on labeling and biodistribution of Re-188-hydroxyethylidene disphosphonate (HEDP)

    International Nuclear Information System (INIS)

    Jang, Y. S.; Jeong, J. M.; Kim, B. K.; Lee, D. S.; Jeong, J. K.; Lee, M. C.; Cho, J. H.

    1998-01-01

    Re-188- hydroxyethylidene disphosphonate (HEDP) is a new cost-effective agent for systemic radioisotope therapy of metastatic bone pain. We investigated the influence of carrier for labeling and biodistribution of Re-188-HEDP using HEDP kit(HEDP 15 mg, gentisic acid 4 mg and SnCl 2 2H 2 O 4.5 mg) with or without carrier (KReO 4 0.1 mg). The kits labeled with Re-188 solution available from an in-house generator by boiling for 15 min. The generator provides high 70-80 % equil yields and has an indefnite self-life. We compared the stability of carrier-added(CA) and carrier-free(CF) preparations of Re-188-HEDP. Biodistribution and imaging studies of each preparation were performed in ICR mice(1.85-3.7 MBq/0.1 ml) and SD rats(74.1-85.2 MBq/0.5 ml). The CA preparation showed high labeling efficiency(95% at pH 5) and high stability in serum(88%, 3 hr). However, the CF preparation showed low labeling efficiency(59% at pH 5) and low stability(43%, 3 hr). The CA preparation showed high uptake in bone and low uptake in stomach and kidneys. However, the CF preparation showed lower uptake in bone and higher uptake in both stomach and kidney, which is supposed to be due to released perrhenate. The CA preparation also showed better images with higher skeletal accumulation, lower uptake in other organs and lower soft tissue uptake than the CF preparation of carrier perrhenate is required for high labeling efficiency, stability, bone uptake and good image quality of Re-188-HEDP

  11. Effect of carrier on labeling and biodistribution of Re-188-Hydroxyethylidene diphosphonate

    International Nuclear Information System (INIS)

    Chang, Young Soo; Jeong, Jae Min; Kim, Bo Kwang; Cho, Jung Hyuk; Lee, Dong Soo; Chung, June Key; Lee, Myung Chul; Lee, Seung Jin; Jin, Ren Jie; Lee, Sang Eun

    2000-01-01

    Re-188-Hydroxyethylidene diphosphonate (HEDP) is a new cost-effective agent for systemic radioisotope therapy of metastatic bone pain. We investigated the influence of carrier for labeling and biodistribution of Re-188-HEDP using HEDP kit with or without carrier (KReO 4 ). The kits (HEDP 15 mg, gentisic acid 4 mg and SnC1 2 .2H 2 O 4.5 mg) with or without carrier (KReO 4 0.1 mg) were labeled with Re-188 solution, made available from an in-house generator by boiling for 15 min. We compared the labeling efficiency and stability of carrier-added and carrier-free preparations of Re-188-HEDP. Biodistribution and imaging studies of each preparation were performed in ICR mice (1.85-3.7 MBq/0.1 ml) and SD rats (74.1-85.2 MBq/0.5 ml). The carrier-added preparation showed high labeling efficiency (95% at pH 5) and high stability in serum (88%, 3hr). However, the carrier-free preparation showed low labeling efficiency (59% at pH 5) and low stability (43%, 3 hr). The carrier-added preparation showed high uptake in bone and low uptake in stomach and kidneys. However, the carrier-free preparation showed lower uptake in bone and higher uptake in both stomach and kidneys, which is supposed to be due to released perrhenate. The carrier-added preparation also showed better images with higher skeletal accumulation, lower uptake in other organs and lower soft tissue uptake than the carrier-free preparation. The results of these studies clearly demonstrate that addition of carrier perrhenate is required for high labeling efficiency, stability, bone uptake and good image quality of Re-188-HEDP.=20

  12. Investigations of labeling insulin-like growth factor-1 analogue with 188Re

    International Nuclear Information System (INIS)

    Zhang Bin; Wu Yiwei; Fan Wo

    2007-01-01

    Objective: To establish a stable method for labeling insulin-like growth factor-1 analogue (IGF-1A) with 188 Re. Methods: The directly labeling method was adopted. Several labeling conditions were tested, such as the volume of Tween-80, the concentration of SnCl 2 ·2H 2 O, the amount of IGF-1A, and the volume of 188 Re perrhenate. The labeling efficiency was determined from 15 min to 8 h after labeling. The in vitro stability of 188 Re-IGF-1A was analyzed by using human serum or sodium chloride as challenging agent, and the labeling efficiency was determined from 2 to 24 h after added challenging agent. Results: The optimum labeling conditions were 10 μl 0.1% Tween-80, 100 μl SnCl 2 · 2H 2 O (10 mg/ml), 50 μl IGF-1A (2 mg/ml), and 50 μl 188 Re perrhenate, incubated 30 min at room temperature. The labeling efficiency of 188 Re-IGF-1A could reach (94.07 ± 0.32)% and the amount of radiocolloid was (5.50 ± 1.50)%. It was (89.07 ± 0.74)% after incubation for 6 h at room temperature, and was (76.57 ± 9.96)% after incubation for 24 h with human serum. Conclusion: This method of labeling IGF- 1A with 188 Re using SnCl 2 ·2H 2 O is stable and high labeling efficiency can be obtained. (authors)

  13. Country Report: Rep. of Korea. {sup 188}re-Tricabonyl Labeling Strategy: Preparation of 1{sup 188}Re(I) Tricarbonyl Precursor [{sup 188}Re(OH{sub 2}){sub 3}(CO){sub 3}]+ for the Labeling of Biomolecules

    Energy Technology Data Exchange (ETDEWEB)

    Park, Sang Hyun [Radiation Research Division for Biotechnology, Korea Atomic Energy Research Institute (Korea, Republic of)

    2010-07-01

    The {sup 99m}Tc(I) and {sup 188}Re(I) tricarbonyl precursors [M(OH{sub 2}){sub 3}(CO){sub 3}]{sup +} have been shown to be excellent starting materials for the synthesis of {sup 99m}Tc(I) and {sup 188}Re(I) tricarbonyl complexes as well as radiolabeling of target-specific biomolecules.{sup 1-8} Recently, a user-friendly kit formulation (IsoLink{sup TM}) was developed using potassium boranocarbonate, K{sub 2}[BH{sub 3}CO{sub 2}], for preparation of the {sup 99m}Tc precursor complex. This solid reagent serves both as a source of carbon monoxide and a reducing agent for technetium. It was also used by Schibli and coworkers for the preparation of the corresponding {sup 188}Re precursor complex (“Schibili’s kit”).{sup 9} This approach involved the reduction of [{sup 188}Re]perrhenate eluate (1 ml) in neutral solution with 3 mg K{sub 2}[BH{sub 3}CO{sub 2}] and 5 mg BH3≅NH3 by incubation at 60 °C for 15 min. The amounts of reducing agents and acid (concentrated phosphoric acid) were carefully balanced not only to avoid fast hydrolysis of the boranes, but also to maintain a sufficiently low pH to stabilize reduced rhenium intermediates. The preparations resulted in yields >85 % of the desired precursor complex. In addition, perrhenate (7±3 %), colloidal {sup 188}ReO{sub 2} (<5 %), and a byproduct of unknown composition were also detected. To increase the yields even further, we evaluated the recently described borohydride exchange resin (BER) as an additional reducing agent and an anion scavengers.

  14. Ion Exchange Distribution Coefficient Tests and Computer Modeling at High Ionic Strength Supporting Technetium Removal Resin Maturation

    Energy Technology Data Exchange (ETDEWEB)

    Nash, Charles A. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Hamm, L. Larry [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Smith, Frank G. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McCabe, Daniel J. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2014-12-19

    The primary treatment of the tank waste at the DOE Hanford site will be done in the Waste Treatment and Immobilization Plant (WTP) that is currently under construction. The baseline plan for this facility is to treat the waste, splitting it into High Level Waste (HLW) and Low Activity Waste (LAW). Both waste streams are then separately vitrified as glass and poured into canisters for disposition. The LAW glass will be disposed onsite in the Integrated Disposal Facility (IDF). There are currently no plans to treat the waste to remove technetium, so its disposition path is the LAW glass. Due to the water solubility properties of pertechnetate and long half-life of 99Tc, effective management of 99Tc is important to the overall success of the Hanford River Protection Project mission. To achieve the full target WTP throughput, additional LAW immobilization capacity is needed, and options are being explored to immobilize the supplemental LAW portion of the tank waste. Removal of 99Tc, followed by off-site disposal, would eliminate a key risk contributor for the IDF Performance Assessment (PA) for supplemental waste forms, and has potential to reduce treatment and disposal costs. Washington River Protection Solutions (WRPS) is developing some conceptual flow sheets for supplemental LAW treatment and disposal that could benefit from technetium removal. One of these flowsheets will specifically examine removing 99Tc from the LAW feed stream to supplemental immobilization. To enable an informed decision regarding the viability of technetium removal, further maturation of available technologies is being performed. This report contains results of experimental ion exchange distribution coefficient testing and computer modeling using the resin SuperLig® 639a to selectively remove perrhenate from high ionic strength simulated LAW. It is advantageous to operate at higher concentration in order to treat the waste

  15. Synthesis, characterization and biological evaluation of [{sup 188}Re(N)(cys{approx})(PNP)]{sup +/0} mixed-ligand complexes as prototypes for the development of {sup 188}Re(N)-based target-specific radiopharmaceuticals

    Energy Technology Data Exchange (ETDEWEB)

    Thieme, Stefan [Institute of Radiopharmacy, Forschungszentrum Dresden Rossendorf, P.O. Box 510 119, 01314 Dresden (Germany); Agostini, Stefania [Department of Pharmaceutical Sciences, University of Padua, Via Marzolo 5, 35131 Padova (Italy); Bergmann, Ralf; Pietzsch, Jens; Pietzsch, Hans-Juergen [Institute of Radiopharmacy, Forschungszentrum Dresden Rossendorf, P.O. Box 510 119, 01314 Dresden (Germany); Carta, Davide; Salvarese, Nicola [Department of Pharmaceutical Sciences, University of Padua, Via Marzolo 5, 35131 Padova (Italy); Refosco, Fiorenzo [ICIS-CNR, Corso Stati Uniti 4, 35127 Padova (Italy); Bolzati, Cristina, E-mail: bolzati@icis.cnr.i [Department of Pharmaceutical Sciences, University of Padua, Via Marzolo 5, 35131 Padova (Italy); ICIS-CNR, Corso Stati Uniti 4, 35127 Padova (Italy)

    2011-04-15

    We report on an efficient procedure for the preparation of [{sup 188}Re(N)(PNP)]-based complexes (where PNP is diphosphinoamine) useful in the development of target-specific radiopharmaceuticals. The radiochemical yield of the compounds was optimized considering such reaction parameters as nature of the nitrido nitrogen donor, reaction times and pH level. The chemical identity of the {sup 188}Re agents was determined by high-performance liquid chromatography comparison with the corresponding well-characterized cold Re compounds. {sup 188}Re(N) mixed compounds have been evaluated with regard to stability toward transchelation with GSH and degradation by serum enzymes. The clearance of selected radiocompounds from normal tissues and their in vivo stability were evaluated in rats by biodistribution and imaging studies. [{sup 188}Re(N)(cys{approx})(PNP)]{sup +/0} mixed-ligand compounds were efficiently prepared in aqueous solution from perrhenate using a multistep procedure based on the preliminary formation of the labile {sup 188}Re{sup III}-EDTA species, which easily undergo oxidation/ligand exchange reaction to afford the [{sup 188}Re{sup V{identical_to}}N]{sup 2+} core in the presence of dithiocarbazate. The final mixed-ligand compounds were obtained, at 100{sup o}C, by adding the two bidentate ligands to the buffered [{sup 188}Re{sup V{identical_to}}N]{sup 2+} solution (pH 3.2-3.6). However, a relatively high amount of cys{approx} ligand was required to obtain a quantitative radiochemical yield. The complexes were stable toward reoxidation to perrhenate and ligand exchange reactions. In vivo studies showed rapid distribution and elimination of the complexes from the body. No specific uptakes in sensitive tissues/organs were detected. A positive correlation of the distribution of the complexes estimated with biodistribution studies (%ID) and with micro-SPECT semiquantification imaging analysis (standard uptake values) was observed. These results support the

  16. 188Re-loaded lipid nanocapsules as a promising radiopharmaceutical carrier for internal radiotherapy of malignant gliomas

    International Nuclear Information System (INIS)

    Allard, E.; Hindre, F.; Passirani, C.; Lemaire, L.; Benoit, J.P.; Lepareur, N.; Noiret, N.; Menei, P.

    2008-01-01

    Lipid nanocapsules (LNC) entrapping lipophilic complexes of 188 Re( 188 Re(S 3 CPh) 2 (S 2 CPh) [ 188 Re-SSS]) were investigated as a novel radiopharmaceutical carrier for internal radiation therapy of malignant gliomas. The present study was designed to evaluate the efficacy of intra-cerebral administration of 188 Re-SSS LNC by means of convection-enhanced delivery (CED) on a 9L rat brain tumour model. Female Fischer rats with 9L glioma were treated with a single injection of 188 Re-SSS LNC by CED 6days after cell implantation. Rats were put into random groups according to the dose infused: 12, 10, 8 and 3Gy in comparison with blank LNC, perrhenate solution (4Gy) and non-treated animals. The radionuclide brain retention level was evaluated by measuring 188 Re elimination in faeces and urine over 72h after the CED injection. The therapeutic effect of 188 Re-SSS LNC was assessed based on animal survival. CED of 188 Re perrhenate solution resulted in rapid drug clearance with a brain T 1/2 of 7h. In contrast, when administered in LNC, 188 Re tissue retention was greatly prolonged, with only 10% of the injected dose being eliminated at 72h. Rat median survival was significantly improved for the group treated with 8Gy 188 Re-SSS LNC compared to the control group and blank LNC-treated animals. The increase in the median survival time was about 80% compared to the control group; 33% of the animals were long-term survivors. The dose of 8Gy proved to be a very effective dose, between toxic (10-12Gy) and ineffective (3-4Gy) doses. These findings show that CED of 188 Re-loaded LNC is a safe and potent anti-tumour system for treating malignant gliomas. Our data are the first to show the in vivo efficacy of 188 Re internal radiotherapy for the treatment of brain malignancy. (orig.)

  17. Plant root absorption and metabolic fate of technetium in plants

    International Nuclear Information System (INIS)

    Cataldo, D.A.; Garland, T.R.; Wildung, R.E.

    1984-10-01

    Root absorption characteristics for the pertechnetate ion (TcO 4 - ) were determined using hydroponically grown soybean seedlings (Glycine max, cv. Williams). Absorption of TcO 4 - was found to be linear with time, sensitive to metabolic inhibitors, and exhibit multiple absorption isotherms over the concentration range 0.02 to 10 μM. The isotherms had calculated K/sub s/ values of 0.09, 8.9, and 54 μM for intact seedlings. The uptake of TcO 4 - (0.25 μM) was inhibited by a fourfold concentration excess of sulfate, phosphate, and selenate, but not by borate, nitrate, tungstate, perrhenate, iodate or vanadate. Kinetic studies demonstrated that sulfate, phosphate, and selenate were competitive inhibitors of TcO 4 - absorption. Once absorbed, Tc was readily transported as TcO 4 - to shoot tissues of soybean and subsequently associated with protein constituents. The chemical fate of Tc in plants varies with plant species. Plants high in nonprotein sulfhydryl compounds (Allium species) exhibited markedly different root/shoot distribution and protein incorporation patterns from species with low sulfur requirements (soybean, alfalfa, mustard). Based on these differences, Tc/S/Se tracer studies were employed to resolve the comparative fate of these probable analogs. 20 references, 5 figures, 5 tables

  18. Use of new tandem cation/anion exchange system with clinical-scale generators provides high specific volume solutions of technetium-99m and rhenium-188

    International Nuclear Information System (INIS)

    Knapp, F.F. Jr.; Beets, A.L.; Mirzadeh, S.; Guhlke, S.

    1998-01-01

    In this paper we describe the first application of our simple and inexpensive post-elution tandem cation/anion exchange column system which is based on generator elution with salts of weak acids such as ammonium acetate instead of saline solution to provide very high specific volume solutions of technetium-99m and rhenium-188 from clinical-scale molybdenum-99/technetium-99m generator prepared from low specific activity (n,y) molybdenum-99, and tungsten-188/rhenium-188 generators, respectively. Initial passage of the bolus through a strong cation exchange cartridge converts the ammonium acetate to acetic acid which is essentially not ionized at the acidic pH, allowing specific subsequent amine-type (QMA SepPak TM ) anion exchange cartridge column trapping of the microscopic levels of the pertechnetate or perrhenate. Subsequent elution of the anion cartridge with a small volume ( 500 mCi/mL) from the alumina-based tungsten-188/rhenium-188 generator. (author)

  19. Upgrade to Ion Exchange Modeling for Removal of Technetium from Hanford Waste Using SuperLig® 639 Resin

    Energy Technology Data Exchange (ETDEWEB)

    Hamm, L. [Savannah River Site (SRS), Aiken, SC (United States); Smith, F. [Savannah River Site (SRS), Aiken, SC (United States); Aleman, S. [Savannah River Site (SRS), Aiken, SC (United States); McCabe, D. [Savannah River Site (SRS), Aiken, SC (United States)

    2013-05-16

    This report documents the development and application of computer models to describe the sorption of pertechnetate [TcO₄⁻], and its surrogate perrhenate [ReO₄⁻], on SuperLig® 639 resin. Two models have been developed: 1) A thermodynamic isotherm model, based on experimental data, that predicts [TcO₄⁻] and [ReO₄⁻] sorption as a function of solution composition and temperature and 2) A column model that uses the isotherm calculated by the first model to simulate the performance of a full-scale sorption process. The isotherm model provides a synthesis of experimental data collected from many different sources to give a best estimate prediction of the behavior of the pertechnetate-SuperLig® 639 system and an estimate of the uncertainty in this prediction. The column model provides a prediction of the expected performance of the plant process by determining the volume of waste solution that can be processed based on process design parameters such as column size, flow rate and resin physical properties.

  20. Separation of technetium from nuclear waste stream simulants. Final report

    International Nuclear Information System (INIS)

    Strauss, S.H.

    1995-01-01

    The author studied liquid anion exchangers, such as Aliquat-336 nitrate, various pyridinium nitrates, and related salts, so that they may be applied toward a specific process for extracting (partitioning) and recovering 99 TcO 4 - from nuclear waste streams. Many of the waste streams are caustic and contain a variety of other ions. For this reason, the author studied waste stream simulants that are caustic and contain appropriate concentrations of selected, relevant ions. Methods of measuring the performance of the exchangers and extractant systems included contact experiments. Batch contact experiments were used to determine the forward and reverse extraction parameters as a function of temperature, contact time, phase ratio, concentration, solvent (diluent), and other physical properties. They were also used for stability and competition studies. Specifically, the author investigated the solvent extraction behavior of salts of perrhenate (ReO 4 - ), a stable (non-radioactive) chemical surrogate for 99 TcO 4 - . Results are discussed for alternate organic solvents; metalloporphyrins, ferrocenes, and N-cetyl pyridium nitrate as alternate extractant salts; electroactive polymers; and recovery of ReO 4 - and TcO 4 -

  1. Separation of tungsten and rhenium on alumina

    Directory of Open Access Journals (Sweden)

    MILOVAN SM. STOILJKOVIC

    2004-09-01

    Full Text Available The conditions for the efficient separation of tungsten(VI and rhenium (VII on alumina were established. The distribution coefficients Kd for tungstate and perrhenate anions, as well as the separation factors a (a = KdWO42-/Kd ReO4- were determined using hydrochloric or nitric acid as the aqueous media. A solution of sodium chloride in the pH range 2–6 was also examined. Under all the tested experimental conditions, alumina is a much better adsorbent for tungsten than for rhenium. The obtained results indicated that the best separation of these two elements is achieved when 0.01– 0.1 mol dm-3 HCl or 1.0 mol dm-3 HNO3 are used as the aqueous media. If NaCl is used as the aqueous phase, the best separation is achieved with 0.20 mol dm-3 NaCl, pH 4–6. Under these experimental conditions, the breakthrough and saturation capacities of alumina for tungsten at pH 4 are 17 and 26 mg W/g Al2O3, respectively. With increasing pH, these values decrease. Thus, at pH 6 they are only 4 and 13 mg W/g Al2O3, respectively.

  2. A study of factors affecting the labelling of tartrate with 188Re and the transchelation of the 188Re from the tartrate to a protein

    International Nuclear Information System (INIS)

    Sailerova, Eva; Billinghurst, M.W.

    2003-01-01

    The formation of 188 Re-tartrate for use in transchelation reactions and the transchelation of the 188 Re onto albumin was studied. Two labelled tartrate products were separated using a non-traditional mobile phase on ITLC strips. Tartrate labelling yield increases with pH but so does the instability when the product is exposed to air. Lower pH's are preferred when oxygen-free labelling conditions can be achieved. Higher tin levels protect against air oxidation. Stability of the Re-tartrate complex is supported by addition of ascorbic acid and ferrous sulphate, however both these agents decreased the rate of the formation of the Re-tartrate complex. The labelling efficiency of a perrhenate solution decreased with the time for which it is stored prior to the labelling reaction, depending on the radioactive concentration. Re-albumin transchelation efficiency increases with the tartrate concentration, while increased stability of the Re-tartrate complex lowers the transchelation yields of Re-albumin

  3. Electrically switched cesium ion exchange

    International Nuclear Information System (INIS)

    Lilga, M.A.; Orth, R.J.; Sukamto, J.P.H.; Schwartz, D.T.; Haight, S.M.; Genders, J.D.

    1997-04-01

    Electrically Switched Ion Exchange (ESIX) is a separation technology being developed as an alternative to conventional ion exchange for removing radionuclides from high-level waste. The ESIX technology, which combines ion exchange and electrochemistry, is geared toward producing electroactive films that are highly selective, regenerable, and long lasting. During the process, ion uptake and elution are controlled directly by modulating the potential of an ion exchange film that has been electrochemically deposited onto a high surface area electrode. This method adds little sodium to the waste stream and minimizes the secondary wastes associated with traditional ion exchange techniques. Development of the ESIX process is well underway for cesium removal using ferrocyanides as the electroactive films. Films having selectivity for perrhenate (a pertechnetate surrogate) over nitrate also have been deposited and tested. A case study for the KE Basin on the Hanford Site was conducted based on the results of the development testing. Engineering design baseline parameters for film deposition, film regeneration, cesium loading, and cesium elution were used for developing a conceptual system. Order of magnitude cost estimates were developed to compare with conventional ion exchange. This case study demonstrated that KE Basin wastewater could be processed continuously with minimal secondary waste and reduced associated disposal costs, as well as lower capital and labor expenditures

  4. Radianttrademark Liquid Radioisotope Intravascular Radiation Therapy System

    International Nuclear Information System (INIS)

    Eigler, N.; Whiting, J.; Chernomorsky, A.; Jackson, J.; Knapp, F.F. Jr.; Litvack, F.

    1998-01-01

    RADIANTtrademark is manufactured by United States Surgical Corporation, Vascular Therapies Division, (formerly Progressive Angioplasty Systems). The system comprises a liquid β-radiation source, a shielded isolation/transfer device (ISAT), modified over-the-wire or rapid exchange delivery balloons, and accessory kits. The liquid β-source is Rhenium-188 in the form of sodium perrhenate (NaReO 4 ), Rhenium-188 is primarily a β-emitter with a physical half-life of 17.0 hours. The maximum energy of the β-particles is 2.1 MeV. The source is produced daily in the nuclear pharmacy hot lab by eluting a Tungsten-188/Rhenium-188 generator manufactured by Oak Ridge National Laboratory (ORNL). Using anion exchange columns and Millipore filters the effluent is concentrated to approximately 100 mCi/ml, calibrated, and loaded into the (ISAT) which is subsequently transported to the cardiac catheterization laboratory. The delivery catheters are modified Championtrademark over-the-wire, and TNTtrademark rapid exchange stent delivery balloons. These balloons have thickened polyethylene walls to augment puncture resistance; dual radio-opaque markers and specially configured connectors

  5. SIMS analysis: Development and evaluation 1995 summary report

    International Nuclear Information System (INIS)

    Groenewold, G.S.; Appelhans, A.D.; Ingram, J.C.; Delmore, J.E.; Dahl, D.A.

    1995-10-01

    Secondary ion mass spectrometry (SIMS) was evaluated for characterizing Hg salts. It was found that sulfate and chloride species could be identified directly without sample preparation. Mercuric oxide could be identified by complexation with formic acid. Hg nitrates could be identified by complexation with cyclohexylamine (CHA). Laser desorption ion trap MS was evaluated for characterizing EDTA on environmental samples. No intact EDTA ions were observed, but a series of EDTA fragment ions were visible, particularly on basalt and soil. An ion trap SIMS was developed: a perrhenate ion gun was interfaced to a Teledyne ion trap spectrometer, and the entire device was mounted on a cart. The technology was demonstrated using a prototype ion trap SIMS instrument for detecting Hg·CHA complexes formed from nitrate salts. Intensity of the ion gun was improved, and the surface damage of the particle was small, and ion gun technology transfer to Phi-Evans, Inc. is being considered. Two technology end users are at INEL's Central Facilities Area 674 pond and acid pit of the Radioactive Waste Management Complex; target problem at both sites is the need for Hg speciation on soil samples

  6. Sodalite as a vehicle to increase Re retention in waste glass simulant during vitrification

    Energy Technology Data Exchange (ETDEWEB)

    Luksic, Steven A., E-mail: steven.luksic@pnnl.gov; Riley, Brian J.; Parker, Kent E.; Hrma, Pavel

    2016-10-15

    Technetium (Tc) retention during Hanford waste vitrification can be increased if the volatility can be controlled. Incorporating Tc into a thermally stable mineral phase, such as sodalite, is one way to achieve increased retention. Here, rhenium (Re)-bearing sodalite was tested as a vehicle to transport perrhenate (ReO{sub 4}{sup −}), a nonradioactive surrogate for pertechnetate (TcO{sub 4}{sup −}), into high-level (HLW) and low-activity waste (LAW) glass simulants. After melting HLW and LAW simulant feeds, the retention of Re in the glass was measured and compared with the Re retention in glass prepared from a feed containing Re{sub 2}O{sub 7}. Phase analysis of sodalite in both these glasses across a profile of temperatures describes the durability of Re-sodalite during the feed-to-glass transition. The use of Re sodalite improved the Re retention by 21% for HLW glass and 85% for LAW glass, demonstrating the potential improvement in Tc-retention if TcO{sub 4}{sup −} were to be encapsulated in a Tc-sodalite prior to vitrification. - Highlights: • Re retention is improved by incorporation into sodalite structure. • LAW-type glass shows lower retention but larger improvement with Re-sodalite. • Sodalite is stable to higher temperatures in high-alumina glass melts.

  7. Rhenium solubility in borosilicate nuclear waste glass: implications for the processing and immobilization of technetium-99.

    Science.gov (United States)

    McCloy, John S; Riley, Brian J; Goel, Ashutosh; Liezers, Martin; Schweiger, Michael J; Rodriguez, Carmen P; Hrma, Pavel; Kim, Dong-Sang; Lukens, Wayne W; Kruger, Albert A

    2012-11-20

    The immobilization of technetium-99 ((99)Tc) in a suitable host matrix has proven to be a challenging task for researchers in the nuclear waste community around the world. In this context, the present work reports on the solubility and retention of rhenium, a nonradioactive surrogate for (99)Tc, in a sodium borosilicate glass. Glasses containing target Re concentrations from 0 to 10,000 ppm [by mass, added as KReO(4) (Re(7+))] were synthesized in vacuum-sealed quartz ampules to minimize the loss of Re from volatilization during melting at 1000 °C. The rhenium was found as Re(7+) in all of the glasses as observed by X-ray absorption near-edge structure. The solubility of Re in borosilicate glasses was determined to be ~3000 ppm (by mass) using inductively coupled plasma optical emission spectroscopy. At higher rhenium concentrations, additional rhenium was retained in the glasses as crystalline inclusions of alkali perrhenates detected with X-ray diffraction. Since (99)Tc concentrations in a glass waste form are predicted to be wastes, assuming Tc as Tc(7+) and similarities between Re(7+) and Tc(7+) behavior in this glass system.

  8. Separation of technetium from nuclear waste stream simulants. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Strauss, S.H. [Colorado State Univ., Fort Collins, CO (United States). Dept. of Chemistry

    1995-09-11

    The author studied liquid anion exchangers, such as Aliquat-336 nitrate, various pyridinium nitrates, and related salts, so that they may be applied toward a specific process for extracting (partitioning) and recovering {sup 99}TcO{sub 4}{sup {minus}} from nuclear waste streams. Many of the waste streams are caustic and contain a variety of other ions. For this reason, the author studied waste stream simulants that are caustic and contain appropriate concentrations of selected, relevant ions. Methods of measuring the performance of the exchangers and extractant systems included contact experiments. Batch contact experiments were used to determine the forward and reverse extraction parameters as a function of temperature, contact time, phase ratio, concentration, solvent (diluent), and other physical properties. They were also used for stability and competition studies. Specifically, the author investigated the solvent extraction behavior of salts of perrhenate (ReO{sub 4}{sup {minus}}), a stable (non-radioactive) chemical surrogate for {sup 99}TcO{sub 4}{sup {minus}}. Results are discussed for alternate organic solvents; metalloporphyrins, ferrocenes, and N-cetyl pyridium nitrate as alternate extractant salts; electroactive polymers; and recovery of ReO{sub 4}{sup {minus}} and TcO{sub 4}{sup {minus}}.

  9. Diphosphonic Acid (HEDP) Complex As A, Bone Pain Palliative Agent

    International Nuclear Information System (INIS)

    H G, Adang; Mutalib, A; Bagiawati, Sri; S, Evi; Aguawarini, Sri; Abidin

    2003-01-01

    Bone pain is a common complication for patient with bone metastases from prostate, breasts, lung and renal cancers. The systemic treatment of metastatic bone cancers can be done by using analgesic drug therapy, hormonal therapy, chemotherapy, narcotic (morphine) and radiopharmaceuticals. Samarium-153 EDTMP is one of the most widely used radiopharmaceutical for the treatment of metallics bone pain. Preparation and quality control of 186 Re-HEDP have been carried out. Radiochemical purity was analysed using paper chromatography and resulted in maximum yields more than 90 % . Complexes quite were stable for 3 days when stored at 4 o C. Rhenium-186 HEDP complex contents in the blood reach optimum activity after 5 minutes and decrease drastically at 24 hours post injection. The complex showed major renal clearance up to 41 % as perrhenate ion within 24 hours after injection, Biodistribution pattern of the injected complex in mice indicates that the accumulated optimum activity in the bone was obtained between 2 - 24 hours post injection, Sterility and pyrogenicity test indicated that the complex were sterile and pyrogen free

  10. Neutron activation determination of rhenium in mineral raw materials of complex composition

    International Nuclear Information System (INIS)

    Shiryaeva, M.B.; Lyubimova, L.N.; Salmin, Yu.P.; Ryumina, K.N.; Tatarkin, M.A.

    1984-01-01

    The method of neutron-activation rhenium determination in mineral raw material of complex composition is developed, according to which easily hydrolized elements: scandium, iron, lanthanum, ytterbium, protactinium, hafnium and partially ruthenium and osmium are isolated in the form of hydroxides after smelting of a sample, which has been previously irradiated in nuclear reactor (thermal neutron flux 1.2x10 13 n/cm 2 xs for 22 hr) with sodium peroxide and leaching of the melt by water. To separate Re from other interfering elements extraction of perrhenate-ion by methylethylketone from alkali solution is used. Interfering effect of gold is eliminated by its extraction with TBP 30% solution in toluence or benzene from 1 M HNO 3 . Activity of rhenium preparations, singled out from samples of comparison, is measured, using multichannel γ-spectrometer with Ge(Li)-coaxial detector of high resolution (approximately 2.0-2.2 keV over the line 122 keV 5+ Co). Relative standard deviation in Re content range 5x10 -7 -5x10 -2 % does not exceed 0.3

  11. 188W→188Re generator for biomedical applications

    International Nuclear Information System (INIS)

    Kamioki, Hiroshi; Mirzadeh, S.; Lambrecht, R.M.; Knapp, R. Jr.; Dadachova, K.

    1994-01-01

    An alumina-based 188 W → 188 Re generator was evaluated for 188 Re yield and elution profile and 188 W breakthrough using various reagents for a three-month period. To address the problem of low specific volume, the generator was eluted with reagents which could be easily destroyed by gentle evaporation from acidic solutions (e.g. NH 4 Cl and NH 4 NO 3 ). We also evaluated a proposed ''alumina/anion-exchange'' tandem generator for the preparation of highly purified 188 Re as perrhenic acid. In parallel studies, the adsorption dynamics of tungsten on alumina showed a sharp rise in the tungsten breakthrough at W/Al 2 O 3 ratio of ∼ 120 mg/g corresponding to a distribution constant of ∼ 8400 from nitrate solution at 0.05 M ionic strength. In adsorption on anion exchange resins, carrier-free 188 Re exhibited a behavior very similar to that of macroscopic quantities of Re. These studies further demonstrated the long and useful shelf-life of 188 W → 188 Re generator. (orig.)

  12. 188W/188Re Generator System and Its Therapeutic Applications

    Directory of Open Access Journals (Sweden)

    A. Boschi

    2014-01-01

    Full Text Available The 188Re radioisotope represents a useful radioisotope for the preparation of radiopharmaceuticals for therapeutic applications, particularly because of its favorable nuclear properties. The nuclide decay pattern is through the emission of a principle beta particle having 2.12 MeV maximum energy, which is enough to penetrate and destroy abnormal tissues, and principle gamma rays (Eγ=155 keV, which can efficiently be used for imaging and calculations of radiation dose. 188Re may be conveniently produced by 188W/188Re generator systems. The challenges related to the double neutron capture reaction route to provide only modest yield of the parent 188W radionuclide indeed have been one of the major issues about the use of 188Re in nuclear medicine. Since the specific activity of 188W used in the generator is relatively low (<185 GBq/g, the eluted Re188O4- can have a low radioactive concentration, often ineffective for radiopharmaceutical preparation. However, several efficient postelution concentration techniques have been developed, which yield clinically useful Re188O4- solutions. This review summarizes the technologies developed for the preparation of 188W/188Re generators, postelution concentration of the 188Re perrhenate eluate, and a brief discussion of new chemical strategies available for the very high yield preparation of 188Re radiopharmaceuticals.

  13. Tc and Re Behavior in Borosilicate Waste Glass Vapor Hydration Tests

    International Nuclear Information System (INIS)

    McKeown, David A.; Buechele, Andrew C.; Pegg, Ian L.; Lukens, Wayne W.; Shuh, David K.

    2007-01-01

    Technetium (Tc), found in some nuclear wastes, is of particular concern with regard to long-term storage, because of its long-lived radioactivity and high mobility in the environment. Tc and rhenium (Re), commonly used as a non-radioactive surrogate for Tc, were studied to assess their behavior in borosilicate glass under hydrothermal conditions in the Vapor Hydration Test (VHT). X-ray absorption spectroscopy (XAS) and scanning electron microscopy (SEM) measurements were made on the original Tc- and Re-containing glasses and their corresponding VHT samples, and show different behavior for Tc and Re under VHT conditions. XAS indicates that, despite starting with different Tc(IV) and Tc(VII) distributions in each glass, the VHT samples have 100% Tc(IV)O 6 environments. SEM shows complete alteration of the original glass, Tc enrichment near the sample surface, and Tc depletion in the center. Perrhenate (Re(VII)O 4 - ) is dominant in both Re-containing samples before and after the VHT, where Re is depleted near the VHT sample surface and more concentrated toward the center. (authors)

  14. Radiant{trademark} Liquid Radioisotope Intravascular Radiation Therapy System

    Energy Technology Data Exchange (ETDEWEB)

    Eigler, N.; Whiting, J.; Chernomorsky, A.; Jackson, J.; Knapp, F.F., Jr.; Litvack, F.

    1998-01-16

    RADIANT{trademark} is manufactured by United States Surgical Corporation, Vascular Therapies Division, (formerly Progressive Angioplasty Systems). The system comprises a liquid {beta}-radiation source, a shielded isolation/transfer device (ISAT), modified over-the-wire or rapid exchange delivery balloons, and accessory kits. The liquid {beta}-source is Rhenium-188 in the form of sodium perrhenate (NaReO{sub 4}), Rhenium-188 is primarily a {beta}-emitter with a physical half-life of 17.0 hours. The maximum energy of the {beta}-particles is 2.1 MeV. The source is produced daily in the nuclear pharmacy hot lab by eluting a Tungsten-188/Rhenium-188 generator manufactured by Oak Ridge National Laboratory (ORNL). Using anion exchange columns and Millipore filters the effluent is concentrated to approximately 100 mCi/ml, calibrated, and loaded into the (ISAT) which is subsequently transported to the cardiac catheterization laboratory. The delivery catheters are modified Champion{trademark} over-the-wire, and TNT{trademark} rapid exchange stent delivery balloons. These balloons have thickened polyethylene walls to augment puncture resistance; dual radio-opaque markers and specially configured connectors.

  15. Incorporation of iridium into electrodeposited rhenium–nickel alloys

    International Nuclear Information System (INIS)

    Cohen Sagiv, Maayan; Eliaz, Noam; Gileadi, Eliezer

    2013-01-01

    Rhenium (Re), a refractory metal that has gained significant recognition as a high performance engineering material, is mostly used in military, aircraft and aerospace applications, as well as for catalysis in the petrochemical industry. However, its performance at high temperature in humid air is limited by the formation of rhenium heptoxide (Re 2 O 7 ), which penetrates the grain boundaries and causes brittleness. Improvement of this is being sought through the incorporation of iridium (Ir) into Re deposits. To this end, suitable plating baths for Re–Ir–Ni coatings were developed. These alloys were deposited from different aqueous solutions on copper substrates under galvanostatic conditions, in a three-electrode cell. The plating bath consisted of iridium tri-chloride, ammonium perrhenate and nickel sulfamate as the electroactive species, and citric acid as the complexing agent. The effects of bath composition and operating conditions on the Faradaic efficiency (FE), partial current densities, as well as on the thickness of the coatings and their composition were studied. Re–Ir–Ni coatings as thick as 18 μm, with Re-content as high as 73 at.% and Ir-content as high as 29 at.%, were obtained, using different plating baths. A mechanism of the electrochemical process was suggested. It was found that both an HCP Ir 0.4 Re 0.6 phase and an HCP Ni phase with nanometric crystallites were formed, possibly together with a hexagonal nickel hydride (Ni 2 H) phase

  16. Ultra-small rhenium nanoparticles immobilized on DNA scaffolds: An excellent material for surface enhanced Raman scattering and catalysis studies.

    Science.gov (United States)

    Anantharaj, S; Sakthikumar, K; Elangovan, Ayyapan; Ravi, G; Karthik, T; Kundu, Subrata

    2016-12-01

    Highly Sensitive and ultra-small Rhenium (Re) metal nanoparticles (NPs) were successfully stabilized in water by the staging and fencing action of the versatile biomolecule DNA that resulted in two distinct aggregated chain-like morphologies with average grain sizes of 1.1±0.1nm and 0.7±0.1nm for the very first time within a minute of reaction time. Re NPs are formed by the borohydride reduction of ammonium perrhenate (NH4ReO4) in the presence of DNA at room temperature (RT) under stirring. The morphologies were controlled by carefully monitoring the molar ratio of NH4ReO4 and DNA. The synthesized material was employed in two potential applications: as a substrate for surface enhanced Raman scattering (SERS) studies and as a catalyst for the reduction of aromatic nitro compounds. SERS study was carried out by taking methylene blue (MB) as the probe and the highest SERS enhancement factor (EF) of 2.07×10(7) was found for the aggregated chain-like having average grain size of 0.7±0.1nm. Catalytic reduction of 4-nitro phenol (4-NP), 2-nitro phenol (2-NP) and 4-nitroaniline (4-NA) with a rate constant value of 6×10(-2)min(-1), 33.83×10(-2)min(-1) and 37.4×10(-2)min(-1) have testified the excellent catalytic performance of our Re NPs immobilized on DNA. The overall study have revealed the capability of DNA in stabilizing the highly reactive Re metal at nanoscale and made them applicable in practice. The present route can also be extended to prepare one dimensional (1-D), self-assembled NPs of other reactive metals, mixed metals or even metal oxides for specific applications in water based solutions. Copyright © 2016 Elsevier Inc. All rights reserved.

  17. Ambient aging of rhenium filaments used in thermal ionization mass spectrometry: Growth of oxo-rhenium crystallites and anti-aging strategies

    Directory of Open Access Journals (Sweden)

    Joseph M. Mannion

    2017-01-01

    Full Text Available Degassing is a common preparation technique for rhenium filaments used for thermal ionization mass spectrometric analysis of actinides, including plutonium. Although optimization studies regarding degassing conditions have been reported, little work has been done to characterize filament aging after degassing. In this study, the effects of filament aging after degassing were explored to determine a “shelf-life” for degassed rhenium filaments, and methods to limit filament aging were investigated. Zone-refined rhenium filaments were degassed by resistance heating under high vacuum before exposure to ambient atmosphere for up to 2 months. After degassing the nucleation and preferential growth of oxo-rhenium crystallites on the surface of polycrystalline rhenium filaments was observed by atomic force microscopy and scanning electron microscopy (SEM. Compositional analysis of the crystallites was conducted using SEM-Raman spectroscopy and SEM energy dispersive X-ray spectroscopy, and grain orientation at the metal surface was investigated by electron back-scatter diffraction mapping. Spectra collected by SEM-Raman suggest crystallites are composed primarily of perrhenic acid. The relative extent of growth and crystallite morphology were found to be grain dependent and affected by the dissolution of carbon into filaments during annealing (often referred to as carbonization or carburization. Crystallites were observed to nucleate in region specific modes and grow over time through transfer of material from the surface. Factors most likely to affect the rates of crystallite growth include rhenium substrate properties such as grain size, orientation, levels of dissolved carbon, and relative abundance of defect sites; as well as environmental factors such as length of exposure to oxygen and relative humidity. Thin (∼180 nm hydrophobic films of poly(vinylbenzyl chloride were found to slow the growth of oxo-rhenium crystallites on the filament

  18. RHENIUM SOLUBILITY IN BOROSILICATE NUCLEAR WASTE GLASS IMPLICATIONS FOR THE PROCESSING AND IMMOBILIZATION OF TECHNETIUM-99 (AND SUPPORTING INFORMATION WITH GRAPHICAL ABSTRACT)

    Energy Technology Data Exchange (ETDEWEB)

    AA KRUGER; A GOEL; CP RODRIGUEZ; JS MCCLOY; MJ SCHWEIGER; WW LUKENS; JR, BJ RILEY; D KIM; M LIEZERS; P HRMA

    2012-08-13

    The immobilization of 99Tc in a suitable host matrix has proved a challenging task for researchers in the nuclear waste community around the world. At the Hanford site in Washington State in the U.S., the total amount of 99Tc in low-activity waste (LAW) is {approx} 1,300 kg and the current strategy is to immobilize the 99Tc in borosilicate glass with vitrification. In this context, the present article reports on the solubility and retention of rhenium, a nonradioactive surrogate for 99Tc, in a LAW sodium borosilicate glass. Due to the radioactive nature of technetium, rhenium was chosen as a simulant because of previously established similarities in ionic radii and other chemical aspects. The glasses containing target Re concentrations varying from 0 to10,000 ppm by mass were synthesized in vacuum-sealed quartz ampoules to minimize the loss of Re by volatilization during melting at 1000 DC. The rhenium was found to be present predominantly as Re7 + in all the glasses as observed by X-ray absorption near-edge structure (XANES). The solubility of Re in borosilicate glasses was determined to be {approx}3,000 ppm (by mass) using inductively coupled plasma-optical emission spectroscopy (ICP-OES). At higher rhenium concentrations, some additional material was retained in the glasses in the form of alkali perrhenate crystalline inclusions detected by X-ray diffraction (XRD) and laser ablation-ICP mass spectrometry (LA-ICP-MS). Assuming justifiably substantial similarities between Re7 + and Tc 7+ behavior in this glass system, these results implied that the processing and immobilization of 99Tc from radioactive wastes should not be limited by the solubility of 99Tc in borosilicate LAW glasses.

  19. Rhenium Re

    International Nuclear Information System (INIS)

    Busev, A.I.; Tiptsova, V.G.; Ivanov, V.M.

    1978-01-01

    The basic methods for determining rhenium in various objects are presented. The gravimetric determination of rhenium is based on a quantitative precipitation of ReO 4 - ions with tetraphenylarsonium chloride. The determination is not hindered by tungstates and molybdates. The potentiometric determination of rhenium in alloys (>=0.5% Re) is based on perrhenate ion reduction to Re(4) with the titrated solution of the Cr(2) salt. Re(7) is titrated in a hot sulfuric acid solution in the presence of KJ. The relative error of the method is 1 to 3%. The photometric determination of rhenium is performed by the rhodamide method in molybdenum-and tungsten-containing alloys and catalytically, in rocks, after it has been separated in the form of sulfide. The extraction-photometric determination of rhenium is carried out with the aid of methyl violet (analysis of a stock with a high content of Mo, W, Ta, Nb, Ti ahd Zr) and thio-oxine (the determination of Re is hindered by Au, Pt, Pd, Ru, Os, Rh, Ir). Also described are methods for differential-spectrophotometric determination of Re with the aid of thiocarbamide, as well as with the aid of dimethylglyoxime in the presence of SnCl 2 in an acid medium when Re is determined in its alloys with niobium and hafnium. It takes 2 hours to analyze the Hf-Re alloy and 3 hours to analyze the Nb-Re alloy, the standard deviation being 0.005 at 30-50% Re and 0.027 to 0.019 at 10-50% Re

  20. Rhenium Uptake as Analogue 96Tc by Steel Corrosion Products

    International Nuclear Information System (INIS)

    K.M. Krupka; C.F. Brown; H. Todd Schaef; S. M. Heald; M. M. Valenta; B. W. Arey

    2006-01-01

    Static batch experiments were used to examine the sorption of dissolved perrhenate [Re(VII)], as a surrogate for pertechnetate [Tc(VII)], on corrosion products of A-516 carbon steel coupons contacted with synthetic groundwater or dilute water. After 109 days of contact time, the concentration of dissolved Re(VII) in the synthetic groundwater matrix decreased by approximately 26%; the dilute water matrix experienced a 99% decrease in dissolved Re(VII) over the same time period. Bulk x-ray diffraction (XRD) results for the corroded steel coupons showed that the corrosion products consisted primarily of maghemite, lepidocrocite, and goethite. Analyses of the coupons by scanning electron microscopy/energy dispersive spectroscopy (SEM/EDS) indicated that Re was present with the morphologically complex assemblages of Fe oxide/hydroxide corrosion products for samples spiked with the highest dissolved Re(VII) concentration (1.0 mmol/L) used for these experiments. Analyses of corroded steel coupons contacted with solutions containing 1.0 mmol/L Re(VII) by synchrotron-based methods confirmed the presence of Re sorbed with the corrosion product on the steel coupons. Analyses showed that the Re sorbed on these corroded coupons was in the +7 oxidation state, suggesting that the Re(VII) uptake mechanism did not involve reduction of Re to a lower oxidation state, such as +4. The results of our studies using Re(VII) as an analogue for 99 Tc(VII) suggest that 99 Tc(VII) would also be sorbed with steel corrosion products and that the inventory of 99 Tc(VII) released from breached waste packages would be lower than what is now conservatively estimated

  1. Anion concurrence and anion selectivity in the sorption of radionuclides by organotones

    International Nuclear Information System (INIS)

    Behnsen, Julia G.

    2007-01-01

    Some long-lived and radiologically important nuclear fission products, such as I-129 (half-life t 1/2 = 1,6 . 10 7 a), Tc-99 (t 1/2 = 2,1 . 10 5 a), and Se-79 (t 1/2 = 6,5 . 10 4 a) are anionic in aqueous environments. This study focuses on the adsorption of such anions to organoclays and the understanding of the selectivity of the process. The organoclays used in this study were prepared from a bentonite (MX-80) and a vermiculite clay, and the cationic surfactants hexadcylpyridium, hexadecyltrimethylammonium, and benzethonium. Surfactant adsorption to the bentonite exceeds the cation exchange capacity of the clay, with the surplus positive charge being balanced by the co-adsorption of chloride. The interlayer distance of the bentonites is increased sufficiently to contain bi- and pseudotrimolecular structures of the surfactants. Adsorption experiments were carried out using the batch technique. Anion adsorption of iodide, perrhenate, selenite, nitrate, and sulphate is mainly due to ion exchange with chloride. As an additional adsorption mechanism, the incorporation of inorganic ion pairs into the interlayer space of the clay is proposed as a result of experiments showing differences in the adsorption levels of sodium and potassium iodide. Anion adsorption results show a clear selectivity of the organoclays, with the affinity sequence being: ReO - 4 > I - > NO - 3 > Cl - > SO 2- 4 > SeO 2- 3 . This sequence corresponds to the sequence of increasing hydration energies of the anions, thus selectivity could be due to the process of minimization of free energy of the system. (orig.)

  2. Preliminary studies with 188Rhenium-tin colloid for radiation synovectomy: preparation, size determination, in vivo distribution, effects and dosimetry studies

    International Nuclear Information System (INIS)

    Mathe, D.; Balogh, L.; Polyak, A.; Kiraly, R.; Andocs, G.; Janoki, G. A.; Chaudhari, P.R.; Perge, E.; Glavits, R.

    2002-01-01

    Generator-produced beta-emitting radionuclides such 188R e are gaining in importance for radiosynoviorthesis because of their availability on a regular basis. We prepared a 188 Re-tin colloid in reaction carried out either at 100 o C or at room temperature (RT). The size of the colloid particles was measured with a laser light-scattering method, and their biodistribution, dosimetric aspects and therapeutic effects were studied in an antigen-induced arthritis (AIA) model in rabbits. 188R e-tin colloid solution was injected intraarticularly into the knee joints of rabbits with AIA and imaging studies were performed. Blood samples were collected post injection for estimation of the blood residence time. We also injected 2 intact rabbits in the same manner with 188R e perrhenate solution in order to observe its effects and distribution in the body. All the treated rabbit knees were subjected to histopathology.The colloid particle size distribution was different after preparation at the different reaction temperatures, with a more suitable mean of 4.53 μm in the RT preparation. The dose delivered to the synovial surface was between 3.51 and 4.21 Gy and that to the bone surface was between 0.70 and 0.84 Gy. Histopathologic examination revealed the development of fibrous connective tissue in the AIA knees 4 weeks after treatment, but not in the control group. The 188R e-tin colloid preparation used in study was suitable for radiation synovectomy application. It requires modifications in the preparation protocol so as to increase the labelling efficiency in correlation with an appropriate particle size. (author)

  3. Electrically switched cesium ion exchange. FY 1997 annual report

    International Nuclear Information System (INIS)

    Lilga, M.A.; Orth, R.J.; Sukamto, J.P.H.

    1997-09-01

    This paper describes the Electrically Switched Ion Exchange (ESIX) separation technology being developed as an alternative to ion exchange for removing radionuclides from high-level waste. Progress in FY 1997 for specific applications of ESIX is also outlined. The ESIX technology, which combines ion exchange and electrochemistry, is geared toward producing electroactive films that are highly selective, regenerable, and long lasting. During the process, ion uptake and elution can be controlled directly by modulating the potential of an ion exchange film that has been electrochemically deposited onto a high surface area electrode. This method adds little sodium to the waste stream and minimizes the secondary wastes associated with traditional ion exchange techniques. Development of the ESIX process is well underway for cesium removal using ferrocyanides as the electroactive films. Films having selectivity for perrhenate (a pertechnetate surrogate) over nitrate also have been deposited and tested. Based on the ferrocyanide film capacity, stability, rate of uptake, and selectivity shown during performance testing, it appears possible to retain a consistent rate of removal and elute cesium into the same elution solution over several load/unload cycles. In batch experiments, metal hexacyanoferrate films showed high selectivities for cesium in concentrated sodium solutions. Cesium uptake was unaffected by Na/Cs molar ratios of up to 2 x 10 4 , and reached equilibrium within 18 hours. During engineering design tests using 60 pores per inch, high surface area nickel electrodes, nickel ferrocyanide films displayed continued durability. losing less than 20% of their capacity after 1500 load/unload cycles. Bench-scale flow system studies showed no change in capacity or performance of the ESIX films at a flow rate up to 13 BV/h, the maximum flow rate tested, and breakthrough curves further supported once-through waste processing. 9 refs., 24 figs

  4. Electrodeposition of rhenium-tin nanowires

    International Nuclear Information System (INIS)

    Naor-Pomerantz, Adi; Eliaz, Noam; Gileadi, Eliezer

    2011-01-01

    Highlights: → Rhenium-tin nanowires were formed electrochemically, without using a template. → The nanowires consisted of a crystalline-Sn-core/amorphous-Re-shell structure. → The effects of bath composition and operating conditions were investigated. → A mechanism is suggested for the formation of the core/shell structure. → The nanowires may be attractive for a variety of applications. - Abstract: Rhenium (Re) is a refractory metal which exhibits an extraordinary combination of properties. Thus, nanowires and other nanostructures of Re-alloys may possess unique properties resulting from both Re chemistry and the nanometer scale, and become attractive for a variety of applications, such as in catalysis, photovoltaic cells, and microelectronics. Rhenium-tin coatings, consisting of nanowires with a core/shell structure, were electrodeposited on copper substrates under galvanostatic or potentiostatic conditions. The effects of bath composition and operating conditions were investigated, and the chemistry and structure of the coatings were studied by a variety of analytical tools. A Re-content as high as 77 at.% or a Faradaic efficiency as high as 46% were attained. Ranges of Sn-to-Re in the plating bath, applied current density and applied potential, within which the nanowires could be formed, were determined. A mechanism was suggested, according to which Sn nanowires were first grown on top of Sn micro-particles, and then the Sn nanowires reduced the perrhenate chemically, thus forming a core made of crystalline Sn-rich phase, and a shell made of amorphous Re-rich phase. The absence of mutual solubility of Re and Sn may be the driving force for this phase separation.

  5. Beta Radiation exposure of medical personnel during vascular brachytherapy with Re-188

    International Nuclear Information System (INIS)

    Moka, D.; Baer, F.; Barth, I.; Rimpler, A.

    2002-01-01

    Intracoronary radiation is currently considered a promising breakthrough approach for preventing restenosis after angioplasty and stenting in patients with severe coronary artery disease. For the therapy of in-stent-restenosis vascular irradiation using balloon catheters filled with liquid radioisotopes provide excellent homogeneity due to the artery stenosis morphology. The radionuclide normally used is a Re-188 solutions (E β ,max=2,12 MeV). To achieve a sufficient dose in the stenosed artery wall (30 Gy in 0.5 mm wall depth) in a tolerable time-scale very high specific activities (>5-10 GBq/ml) of the isotope are necessary. During the preparation of the radioactive solution and the application at the patient very short distances between the source of the radiation and the skin of the doctors for cardiology / nuclear medicine are possible, especially when manipulations at the balloon catheter during the radiation are necessary. In addition, a severe risk of contamination exists. A further problem is that in hospitals often no or insufficient dosimeters for beta radiation are available. Occupational radiation exposure of the personnel was determined at the preparation of the Re-188 solution, the therapy itself and the waste management. The partial body exposure, i. e. the dose of the skin at the hands due to beta radiation, was determined with very sensitive thin-layer thermoluminescence dosimeters (TLD). During a preparation, intracoronary radiation and waste management of the Re-188-perrhenate solution using normal radiation shielding first measurements resulted din more than 500 mSv per working day at the fingertips. This extreme high radiation exposure of the personnel were mainly due to direct radiation by touching the evacuated balloon catheter (only residual radionuclides left). to reduced radiation we performed several additional radiation protection measures. The consequent use of plastic shielding of the source, the use of a semiautomatic preparation

  6. Liposomes as carriers of the beta-emitters rhenium-186 and rhenium-188 for use in radiotherapy

    International Nuclear Information System (INIS)

    Haefeli, U.

    1989-01-01

    The two radioisotopes Re-186 and Re-188 are highly favoured as therapeutic nuclides in nuclear medicine due to their unique radiation characteristics. For application in future (e.g. radiosynoviorthesis of the knee) we have chosen liposomes as biodegradable and non-irriting carriers. They were filled with radioactive Re in therapeutic doses of >370 MBq (10 mCi). 1. Small unilamellar liposomes (SUV's) of an average size of 28 nm were prepared by ultrasonic irradiation. They encapsulated only 0.64% of the perrhenate. 2. Liposomes carrying DTPA-SA in their bilayer (SA=octadecylamine) were produced in order to form a complex with Tc and Re. Technetium was complexed in high yield and the Tc-DTPA-liposome bindings were found to be stable when tested by dialysis. Similar attempts to complex Re were not successful because the amount of Sn(+II) required for the reduction was so high that the liposomes were destroyed. 3. Methylthiosemicarbazide (mts) was coupled covalently to aminomethylpolystyrene. These spheres were used as a very convenient and simple model for testing the labelling-yield and the stability of the Re-mts-complex. 4. Two isomers of the complex ReO(OEt)Cl 2 (PPh 3 ) 2 (Rephos) were characterized. These highly lipid-soluble inactive complexes were irradiated by neutrons and then used to prepare a mixed micelle with egg yolk lecithin and the detergent sodium deoxycholate. Liposomes were produced in a size of 60-80 nm in a very simple way by gelfiltration. Up to 53.5% of the radioactive Rephos was incorporated. Monitoring the stability by dialysis an initial loss of 10-15% and subsequent linear decrease were observed. The daily loss could be reduced to 1.0% by the addition of ascorbic acid. After 8 days, 82% of the initial activity still remained in the vesicles. 5. [ReO 2 (en) 2 ]Cl.2H 2 O and [ReO 2 (1,4,8,11-tetraazaundecane)]Cl were synthesized and characterized. 6. A direct enzymatic method to determine the remaining cholate in liposomes was developed

  7. {sup 186}Re-maSGS-Z{sub HER2:342}, a potential affibody conjugate for systemic therapy of HER2-expressing tumours

    Energy Technology Data Exchange (ETDEWEB)

    Orlova, Anna; Tran, Thuy A. [Uppsala University, Division of Biomedical Radiation Sciences, Rudbeck Laboratory, Uppsala (Sweden); Ekblad, Torun; Karlstroem, Amelie Eriksson [Royal Institute of Technology, School of Biotechnology, Division of Molecular Biotechnology, Stockholm (Sweden); Tolmachev, Vladimir [Uppsala University, Division of Biomedical Radiation Sciences, Rudbeck Laboratory, Uppsala (Sweden); Uppsala University, Division of Nuclear Medicine, Department of Medical Sciences, Uppsala (Sweden)

    2010-02-15

    Affibody molecules are a novel class of tumour-targeting proteins, which combine small size (7 kDa) and picomolar affinities. The Affibody molecule Z{sub HER2:342} has been suggested for imaging of HER2 expression in order to select patients for trastuzumab therapy. When optimizing chelators for {sup 99m}Tc-labelling, we have found that synthetic Z{sub HER2:342} conjugated with mercaptoacetyl-glycyl-glycyl-glycyl (maGGG) and mercaptoacetyl-glycyl-seryl-glycyl (maGSG) chelators provides relatively low renal uptake of radioactivity and could be suitable for therapy. maGGG-Z{sub HER2:342} and maGSG-Z{sub HER2:342} were labelled with {sup 186}Re and their biodistribution was studied in normal mice. Dosimetric evaluation and tumour targeting to HER2-overexpressed xenografts (SKOV-3) by {sup 186}Re-maGSG-Z{sub HER2:342} were studied. Gluconate-mediated labelling of maGGG-Z{sub HER2:342} and maGSG-Z{sub HER2:342} with {sup 186}Re provided a yield of more than 95% within 60 min. The conjugates were stable and demonstrated specific binding to HER2-expressing SKOV-3 cells. Biodistribution in normal mice demonstrated rapid blood clearance, low accumulation of radioactivity in the kidney and other organs, accumulating free perrhenate. Both {sup 186}Re-maGGG-Z{sub HER2:342} and {sup 186}Re-maGSG-Z{sub HER2:342} demonstrated lower renal uptake than their {sup 99m}Tc-labelled counterparts. {sup 186}Re-maGSG-Z{sub HER2:342} provided the lowest uptake in healthy tissues. Biodistribution of {sup 186}Re-maGSG-Z{sub HER2:342} in nude mice bearing SKOV-3 xenografts showed specific targeting of tumours. Tumour uptake 24 h after injection (5.84{+-}0.54%ID/g) exceeded the concentration in blood by more than 500-fold, and uptake in kidneys by about 8-fold. Preliminary dosimetric evaluation showed that dose-to-tumour should exceed dose-to-kidney by approximately 5-fold. Optimization of chelators improves biodistribution properties of rhenium-labelled small scaffold proteins and enables

  8. Rhenium-188 - advantages and clinical potential for use of a readily available, cost effective therapeutic radioisotope for applications in nuclear medicine, oncology and interventional cardiology

    International Nuclear Information System (INIS)

    Knapp, F.F. jr.

    2002-01-01

    Full text: Carrier-free rhenium-188 (Re-188) is readily available from the alumina-based tungsten-188/rhenium-188 generator system and has many attractive properties for a wide variety of therapeutic applications. The 16.9 h half-life, emission of the 2.2 MeV beta particle and versatile chemistry make Re-188 an important candidate for applications where high radiation penetration is required. In addition, emission of a gamma photon (155 KeV, 15 %) permits evaluation of biodistribution, pharmacokinetics and dosimetry estimates. The long physical half-life of the tungsten-188 (W-188) parent (t 1/2 69 days) and consistent generator performance - with high Re-188 yields and low W-188 parent breakthrough - result in an indefinite shelf-life of several months, dependent on the levels of Re-188 required. Post generator elution in-growth of 62 % of Re-188 after 24 hours in combination with high elution yields (75-85 %) result in 50 % daily yields of the maximal Re-188 available. In addition to research being conducted for the development of a wide variety of new therapeutic radiopharmaceuticals and devices, Re-188 is also being evaluated in physician-sponsored clinical trials in over 15 countries, with applications in nuclear medicine, oncology and interventional cardiology. One major current clinical application involves post-angiographic treatment of arterial segments following PTCA using Re-188 perrhenate or MAG3 liquid-filled balloons as an effective and cost-effective approach for inhibition of the hyperplastic response to vessel damage, which delivers uniform dose to the vessel wall. Re-188-HEDP is being used for palliation of metastatic bone pain palliation. This agent is readily prepared from a simple 'kit' and provides pain palliation as effective as other commercially available agents. The use of the Re-188-labeled Anti-NCA-95 antibody (BW 50/183; CD66 a,b,c,e) in conjunction which external beam irradiation and chemotherapy is an effective method for

  9. MAG2GABA-biocytin synthesized with new intermediates for radiolabelling 99mTc and 188Re

    International Nuclear Information System (INIS)

    Ahn, S.H.; Choi, T.H.; Choi, C.W.; Yang, S.D.; Woo, K.S.; Chung, W.S.; Lim, S.M.

    2001-01-01

    188 Re from 188 W- 188 Re generator, is recently introduced in therapeutic nuclear medicine and made it possible to use whenever needed. We synthesized MAG 2 GABA-Biocytin (MGB), labelled with 188 Re for pretargeted radioimmunotherapy and evaluated biological behavior of 188 Re-MGB. N-hydroxysuccinimidyl ester of S-benzoyl mercaptoacetyldiglycine (NHS-MAG 2 ) was synthesized first, reacted with aminobutyric acid(GABA) to give MAG 2 GABA and then converted to NHS-MAG 2 GABA and conjugated to biocytin to give the MGB. To label MGB with 188 Re (50mA), ag, 200ml 1M tartrate pH7, 200 l stannous (10mg/mL) and 180MBq perrhenate were mixed and heated for 30min at 100 deg. C. The reactant was purified with C 18 Sep-Pak. HPLC analysis of the 188 Re-MGB performed on reverse phase C 18 column with a gradient. To see the stability, 188 Re-MGB was added to serum at 37 deg. C. Binding capacity of 188 Re-MGB to avidin or streptavidin was determined by size exclusion HPLC system. Biodistribution was studied in ICR normal mice(n=4/group), from 5min to 120min. In Raji cells tumour bearing nude mice(n=3), biotinylated Lym-1(40MEG) injection after 48 h, streptavidin(50MEG) was injected. 24 h later, 188 Re-MGB(0.5MEG) was injected, and biodistribution was observed 2 h later. 188 Re-MGB was obtained with labelling yield 98%. Stability in serum was maintained over 70% until 3 h. Binding capacity of 188 Re-MGB to streptavidin was greater than avidin. In normal mice, 188 Re-MGB was excreted via hepatobiliary pathway,%ID/g of GI tract was 52.1 at 120min. In Raji cells tumour bearing nude mice, liver and colon were higher than those of normal mouse. Tumour uptake at 120min was 0.05%ID/g. 188 Re-MGB was effectively labelled and retained binding activity with streptavidin. 188 Re-MGB may have a role in pretargeted radioimmunotherapy. (author)

  10. Chromatographic 188W →188Re generator

    International Nuclear Information System (INIS)

    Khujaev, S.

    2005-01-01

    Full text: The main purpose of the generator - reception of daughter radioisotope Rhenium-188 from it by periodic elution for a long period of time (more than half-year). It is generally known that Rhenium-188, in the form of its complex connections, is applied in nuclear medicine in treatment and removal of painful syndromes. The generator possesses convenient nuclear-physical characteristics of a daughter radioisotope Rhenium-188. It is a source of (Irradiation with energy 2.12 MeV (98 %) with small contribution soft γ-radiation with energy 0.155 MeV (15 %). The Period of half-life destruction of radioisotope is 17 hours. The 188 W parent radioisotope for the generator is formed by irradiation of 186 W neutrons based on the following reaction: 186 W (n,γ) 187 W (n,γ) 188 W (69 days) → 188 Re (17 hours) + β The following were used as targets for irradiation: 1) Metal Tungsten (powder) of natural structure; 2) Metal Tungsten (plate) of natural structure; 3) Metal Tungsten (wire) of natural structure, d = 12 mm; 4) Metal Tungsten (powder) with enrichment on isotope 186 W - 99.79 %. The irradiated material was exposed to chemical processing with reception of radioactive solution of tungsten-188, from which sorption Tungsten was carried out onto sorbent as poly-wolframate-ions. It is established that Tungsten sorption depends on many factors as there are various chemical forms of Tungsten (VI) in water solutions, ratio of which depends on pH of the solution, concentration of Tungsten in the solution and presence of foreign ions. Tungsten sorption was carried out in static and in dynamic regimes. At dynamic regime the sorbent was placed directly in the generating column. The generator consisted of chromatographic columns with sorbent and radioisotope 188 W, eluting system and radiation protection. Rhenium-188 was taken from the generator as perrhenate sodium by elution of 0.9 % solution of chloride sodium in 10 ml. Technical characteristics of the generator

  11. The Dresden in-stent restenosis radiation trial (DIRRT) with liquid-filled 188Re balloon

    International Nuclear Information System (INIS)

    Kropp, J.; Runge, R.R.; Reynen, K.; Koeckeritz, U.; Schmeisser, A.; Strasser, R.H.

    2002-01-01

    Full text: In some studies intracoronary radiation therapy (IRT) to minimize the restenosis rate after PTCA proved to be effective. We evaluated the performance, safety and effectiveness of IRT with 188 Re-perrhenate filled into a standard PTCA balloon. This kind of IRT allows a self-centering homogenous dose distribution to the vessel wall. 107 patients (pts) with a mean age of 63 years (81 m, 26 fin) with in-stent restenosis (type B in 39 %, type C in 61 %) and proven ischemia were included. After routine re-PTCA with or without additional stent implantation a second standard balloon was placed into the PTCA area and filled with β - -emitting liquid 188 Re at 3 atm. Irradiation time was 525 ± 167 sec to achieve a dose of 30 Gy at 0.5 mm depth of the vessel wall. In only one procedure there was a disconnection of the 188 Re containing system and the catheter but no contamination of the cath table or lab was measured. In 16 coronaries 21 stents were additionally implanted. In the follow-up 4 stent thromboses (1 day, 37 days, 2 x 6 months) with subsequent myocardial infarction were noticed, all in pts with additionally implanted stents. 57 pts had control angiography after 4 to 6 months after therapy and 41 after one year. Restenosis (stenosis > 50 % of luminal diameter) was shown in 9 out of 12 pts (75 %) with additionally implanted stents but only in 4 out of 24 pts (17 %) with PTCA alone. Reocclusion was noticed in 3 (25 %) pts with additional stent but only in 1 pt (4 %) without. No re-restenosis occurred in 20 patients which were without finding after 6 months. Intracoronary radiation therapy (IRT) with β - -emitting liquid-filled 188 Re balloon is a safe and effective therapy method which might be used routinely. Long-term results seem satisfactory in a patient group with in-stent restenosis and high risk of re-restenosis. But the positive effect of irradiation is abolished if an additional stent after PTCA is needed. (author)

  12. Preparation and initial characterization of fluidized bed steam reforming pure-phase standards

    Energy Technology Data Exchange (ETDEWEB)

    Missimer, D. M.; Rutherford, R. L.

    2013-03-21

    Hanford is investigating the Fluidized Bed Steam Reforming (FBSR) process for their Low Activity Waste. The FBSR process offers a low-temperature continuous method by which liquid waste can be processed with the addition of clay into a sodium aluminosilicate (NAS) waste form. The NAS waste form is mainly comprised of nepheline (NaAlSiO{sub 4}), sodalite (Na{sub 8}[AlSiO{sub 4}]{sub 6}Cl{sub 2}), and nosean (Na{sub 8}[AlSiO{sub 4}]{sub 6}SO{sub 4}). Anions such as perrhenate (ReO{sub 4}{sup -}), pertechnetate (TcO{sub 4}{sup -}), and iodine (I{sup -}) are expected to replace sulfate in the nosean structure and/or chloride in the sodalite mineral structure (atomically bonded inside the aluminosilicate cages that these mineral structures possess). In the FBSR waste form, each of these phases can exist in a variety of solid solutions that differ from the idealized forms observed in single crystals in nature. The lack of understanding of the durability of these stoichiometric or idealized mineral phases complicates the ability to deconvolute the durability of the mixed phase FBSR product since it is a combination of different NAS phases. To better understand the behavior, fabrication and testing of the individual phases of the FBSR product is required. Analytical Development (AD) of the Science and Technology directorate of the Savannah River National Laboratory (SRNL) was requested to prepare the series of phase-pure standards, consisting of nepheline, nosean, and Cl, Re, and I sodalite. Once prepared, X-ray Diffraction (XRD) analyses were used to confirm the products were phase pure. These standards are being used for subsequent characterization studies consisting of the following: single-pass flow-through (SPFT) testing, development of thermodynamic data, and x-ray diffraction (XRD) calibration curves. In addition to the above mentioned phase-pure standards, AD was tasked with fabricating a mixed Tc-Re sodalite.

  13. Preparation of cyclotron-produced {sup 186}Re and comparison with reactor-produced {sup 186}Re and generator-produced {sup 188}Re for the labeling of bombesin

    Energy Technology Data Exchange (ETDEWEB)

    Moustapha, Moustapha E. [Department of Chemistry, University of Missouri-Columbia, Columbia, MO 65211 (United States); University of Missouri Research Reactor (MURR), University of Missouri-Columbia, Columbia, MO 65211 (United States); Ehrhardt, Gary J. [Department of Chemistry, University of Missouri-Columbia, Columbia, MO 65211 (United States); University of Missouri Research Reactor (MURR), University of Missouri-Columbia, Columbia, MO 65211 (United States); Smith, Charles J. [Department of Radiology, University of Missouri-Columbia, Columbia, MO 65211 (United States); University of Missouri Research Reactor (MURR), University of Missouri-Columbia, Columbia, MO 65211 (United States); Research Services, Harry S. Truman Memorial Veterans' Hospital, Columbia, MO 65201 (United States); Szajek, Lawrence P. [Positron Emission Tomography Department, National Institutes of Health, Bethesda, MD 20892-1180 (United States); Eckelman, William C. [Positron Emission Tomography Department, National Institutes of Health, Bethesda, MD 20892-1180 (United States); Jurisson, Silvia S. [Department of Chemistry, University of Missouri-Columbia, Columbia, MO 65211 (United States)]. E-mail: jurissons@missouri.edu

    2006-01-15

    The radioisotopes {sup 186}Re and {sup 188}Re have been extensively investigated for various forms of radiotherapy due to their useful and high-abundance {beta} particle emissions, low-abundance and imageable {gamma}-rays, and chemical resemblance to technetium. In addition, {sup 188}Re is available in no-carrier-added (NCA) form from long lived W-188 generators, whereas {sup 186}Re can be produced in large quantities from reactors, although not in NCA form. However, NCA {sup 186}Re can be produced on a cyclotron by a (p,n) reaction on {sup 186}W. The purpose of this study was to compare labeling of the peptide bombesin with these three forms of rhenium radioisotopes. Cyclotron-produced NCA {sup 186}Re was separated radiochemically from enriched {sup 186}W (96.9%) targets using high-purity methyl ethyl ketone (MEK). The resulting {sup 186}Re-MEK was then loaded onto a small alumina column to separate the resulting NCA {sup 186}Re from any remaining {sup 186}W. The experimental levels of impurities associated with {sup 186}Re at the end of the separation process were found to be 5.7x10{sup -6} Ci of {sup 182}Re (0.57%, t {sub 1/2}=12.7 h) and 1.283x10{sup -5} Ci of {sup 182m}Re (1.28%, t {sub 1/2}=2.67 days). The radionuclidic purity of the separated {sup 186}Re was found to be 99.6%, whereas the chemical identity was determined by reversed phase high-performance liquid chromatography (RP-HPLC) to be perrhenate ({sup 186}ReO{sub 4} {sup -}). Generator-produced {sup 188}ReO{sub 4} {sup -} from a {sup 188}W/{sup 188}Re generator (Oak Ridge National Laboratory) and CA {sup 186}ReO{sub 4} {sup -} produced from a {sup 185}Re(n,{gamma}){sup 186}Re reaction at the University of Missouri Research Reactor (MURR) were used for comparison with the NCA {sup 186}Re in subsequent studies. N{sub 3}S-5-Ava-BBN(7-14)NH{sub 2} conjugates provide flexibility for designing {sup 186,188}Re-labeled conjugates that retain high in vitro and in vivo specificity targeting of GRP receptor

  14. PEGylated N-methyl-S-methyl dithiocarbazate as a new reagent for the high-yield preparation of nitrido Tc-99m and Re-188 radiopharmaceuticals

    Energy Technology Data Exchange (ETDEWEB)

    Boschi, Alessandra, E-mail: alessandra.boschi@unife.i [Laboratory of Nuclear Medicine, Department of Radiological Sciences, University of Ferrara, 44100 Ferrara (Italy); Massi, Alessandro [Department of Chemistry, University of Ferrara, 44100 Ferrara (Italy); Uccelli, Licia; Pasquali, Micol; Duatti, Adriano [Laboratory of Nuclear Medicine, Department of Radiological Sciences, University of Ferrara, 44100 Ferrara (Italy)

    2010-11-15

    A novel nitrido nitrogen atom donor for the preparation of {sup 99m}Tc and {sup 188}Re radiopharmaceuticals containing a metal-nitrogen multiple bond is presented. HO{sub 2}C-PEG{sub 600}-DTCZ was obtained by conjugation of N-methyl-S-methyl dithiocarbazate [H{sub 2}N-N(CH{sub 3})-C({identical_to}S)SCH{sub 3}, HDTCZ] with polyethylene glycol 600 (PEG{sub 600}). Asymmetrical heterocomplexes of the type [M(N)(PNP)(B)]{sup 0/+} (M={sup 99m}Tc, {sup 188}Re; PNP=diphosphine ligands, B=DBODC, DEDC, NSH, H{sub 2}OS, CysNAc, HDTCZ) and symmetrical nitride compounds of the type [M(N)(L){sub 2}] (L=DEDC, DPDC) have been prepared in high yield by using the newly designed nitride nitrogen atom donor HO{sub 2}C-PEG{sub 600}-DTCZ. A two-step procedure was applied for preparing the above symmetrical and asymmetrical complexes. The first step involved the preliminary formation of a mixture of nitride Tc-99m or Re-188 precursors, which contained the [M{identical_to}N]{sup 2+} core, through reduction of generator-eluted {sup 99m}Tc-pertechnetate or {sup 188}Re-perrhenate with thin (II) chloride in the presence of HO{sub 2}C-PEG{sub 600}-DTCZ. In the second step, the intermediate mixture was converted either in the final mixed asymmetrical complex by the simultaneous addition of diphosphine ligand and the suitable bidentate ligand B, or in the final symmetrical complex by the only addition of the bidentate ligand L. It was also demonstrated that the novel water-soluble nitride nitrogen atom donor HO{sub 2}C-PEG{sub 600}-DTCZ did not show coordinating properties toward the M{identical_to}N ({sup 99m}Tc, {sup 188}Re) core. Biodistribution studies in rats of the hitherto unreported [{sup 99m}Tc(N)(PNP{sub 3})DTCZ]{sup +} and [{sup 99m}Tc(N)(PNP{sub 5})DTCZ]{sup +} complexes showed that they selectively localize in the myocardium of rats with a favourable heart-to-lung and heart-to-liver uptake ratios. In particular, the heart-to-lung and heart-to-liver uptake ratios dramatically

  15. The predicted effects of selected Phebus FPT1 sump constituents on iodine volatility

    Energy Technology Data Exchange (ETDEWEB)

    Cripps, R.C., E-mail: csfkge1504@bluewin.ch; Güntay, S., E-mail: salih.guentay@psi.ch; Jäckel, B., E-mail: bernd.jaeckel@psi.ch

    2014-06-01

    irradiated and sparged CsI solutions at pH 4.6 produce lower %I{sub 2} yields with increasing perrhenate ion concentration. In conclusion, these results show that predicted iodine chemistry in the aqueous phase can be significantly affected by including additional models to simulate reactions between iodine and metallic species, which were reported in the Phebus FPT1 post-test sump. These models are first attempts and although most of the corresponding kinetic data were literature-sourced, some were “informed estimates”. Thus no claim is made for direct insertion of these models into established iodine prediction codes. Nevertheless, the authors hope that the results highlight the need for in-depth experimental and modelling studies of these and possibly other metallic sump constituents or suppression pools, that is, in research areas, which were hitherto relatively unexplored.’.

  16. Production of radionuclides with generators

    International Nuclear Information System (INIS)

    Khujaev, S.; Egamediev, S.Kh.

    2004-01-01

    (75-85%) independently of the 99 Mo activity (250 - 1000 mCi) at the beginning and the end (up to 15 days) of the period of use. 188 W- 188 Re generator. 188 Re (T 1/2 =16.9 hours, β - m ax=2.12 MeV; γ=155 keV, 15%) is currently attractive radionuclide for radiotherapeutic applications. Rhenium-188 is produced by decay of tungsten-188 (T 1/2 =69.4 d) which can be produced by double neutron capture on enriched 188 W targets with high neutron flux. The specific activity of 188 W is reached up to 2 Ci/g. The optimal conditions for separation of 188 Re from the parent nuclide 188 W are studied. It is shown that the optimal separation condition is using acid-treated aluminium-oxide column to adsorb 188 W as isopolytungstate at pH solution of 2-4. 188 Re is eluted with 0.9% NaCl solution. The characteristics of the sodium perrhenate obtained from our generator are: radiochemical purity is 99.8%; pH 4.0-6.0; yield of 188 Re is 70-75%; breakthrough of 188 W is less than 10 -3 %. 68 Ge- 68 Ga generator. The nuclide 68 Ga (T 1/2 =68.3 min) produced by the electron capture decay of 68 Ge (T 1/2 =288 d) is useful for calibrating positron emission tomography (PET) systems. The 68 Ge is normally produced by both 66 Zn(α,2n) 68 Ge and 69 Ga(p,2n) 68 Ge nuclear reactions. The separation of daughter 68 Ga from parent 68 Ge on both aluminium oxide and tin dioxide are studied. In case of tin dioxide the optimal separation of daughter 68 Ga from parent 68 Ge can be achieved by using 1 M HCl as the eluent. It is shown that the tin dioxide - 1 M HCl generator system provides high yields of 68 Ga (75-80%) with low levels of breakthrough of 68 Ge (2 · 10 -4 %). However, the obtained final product - 68 Ga eluate in 1 M HCl can not be used for direct preparation of radiopharmaceuticals. In case of aluminium oxide we have found that preliminary annealing of aluminium oxide at 1000 deg C provides the best conditions for separation of 68 Ge- 68 Ga radionuclide chain in 0.1 M hydrochloric acid

  17. Immobilization and Limited Reoxidation of Technetium-99 by Fe(II)-Goethite

    International Nuclear Information System (INIS)

    Um, Wooyong; Chang, Hyun-shik; Icenhower, Jonathan P.; Qafoku, Nikolla; Smith, Steven C.; Serne, R. Jeffrey; Buck, Edgar C.; Kukkadapu, Ravi K.; Bowden, Mark E.; Westsik, Joseph H.; Lukens, Wayne W.

    2010-01-01

    This report summarizes the methodology used to test the sequestration of technetium-99 present in both deionized water and simulated Hanford Tank Waste Treatment and Immobilization Plant waste solutions. Synthesized goethite, α-FeOOH, was successfully used with the addition of aqueous Fe(II) to sequester technetium (Tc) present in both deionized water and waste solutions simulated to represent tank waste solutions derived from low-activity-waste glass melter off-gas scrubbers used at the Hanford Tank Waste Treatment and Immobilization Plant (WTP). Perrhenate, Re(VII), was also tested as a nonradiological surrogate of pertechnetate (Tc(VII)). In a slurry of goethite and dissolved Fe(II), Tc(VII) concentrations in solution decreased immediately when the slurry pH was raised above 7.0 by adding sodium hydroxide (NaOH). The total amount of Tc present in the final solid as determined by acid digestion showed a high degree of Tc sequestration, 90% to 100%, in the final Tc-goethite solids. In contrast, a relatively small percentage (0% to 43%) of Re removal was found even though the Re-goethite solid was prepared by the same method as the Tc-goethite. The difference in sequestration is caused by the different Re solubility and redox potential vs pH. Removal of Tc(VII) from solution occurred most likely as a result of heterogeneous surface-catalyzed reduction to Tc(IV) and subsequent co-precipitation with newly formed magnetite or goethite during the Fe(II) treatment and pH adjustment. One of the final Tc-goethite products, Sample 2-5, was subsequently armored through a mineral transformation process that involved adding additional Fe(III) and NaOH to isolate the reduced Tc(IV) from future oxidizing agents. Although the dominant major mineral in Tc-goethite samples prepared without armoring was magnetite, the final Tc-bearing solid in Tc-goethite samples prepared with the additional armoring process was identified as goethite-dominated Fe(III)-(oxy)hydroxide based on x