Abstract As a part of NEXT, the behavior of Np in a simplified solvent extraction process using TBP as an extractant for U, Pu and Np co-recovery was investigated. Two approaches to Np co-recovery with U and Pu in the irradiated fast reactor core fuel using a dissolver solution in a counter current were examined. One used a feed solution with a high HNO3 concentration, and the other used a scrubbing solution with a high HNO3 concentration. The leakages of Np to the raffinate were 1.1 and 4.7% using high HNO3 concentration feed and scrubbing solutions, respectively. Simulation results based on these experiments showed that high HNO3 concentration in the feed solution is advantageous for the Np extraction because Np oxidation progresses in the feed solution before being supplied into the centrifugal contactor, and there is less effect of HNO2 at the extraction section.
{"title":"Uranium, plutonium and neptunium co-recovery with high nitric acid concentration in extraction section by simplified solvent extraction process","authors":"M. Nakahara, Y. Sano","doi":"10.1524/RACT.2009.1671","DOIUrl":"https://doi.org/10.1524/RACT.2009.1671","url":null,"abstract":"Abstract As a part of NEXT, the behavior of Np in a simplified solvent extraction process using TBP as an extractant for U, Pu and Np co-recovery was investigated. Two approaches to Np co-recovery with U and Pu in the irradiated fast reactor core fuel using a dissolver solution in a counter current were examined. One used a feed solution with a high HNO3 concentration, and the other used a scrubbing solution with a high HNO3 concentration. The leakages of Np to the raffinate were 1.1 and 4.7% using high HNO3 concentration feed and scrubbing solutions, respectively. Simulation results based on these experiments showed that high HNO3 concentration in the feed solution is advantageous for the Np extraction because Np oxidation progresses in the feed solution before being supplied into the centrifugal contactor, and there is less effect of HNO2 at the extraction section.","PeriodicalId":21029,"journal":{"name":"Radiochimica Acta Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2009-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"76007528","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
A. Rout, K. Venkatesan, T. Srinivasan, P. Vasudeva Rao
Abstract Extraction of americium(III) from nitric acid medium by a solution of tri-n-butylphosphate (TBP) and n-octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (CMPO) in room temperature ionic liquid, 1-butyl-3-methylimidazolium bis(trifluoromethanesulfonyl)imide (bmimNTf2), was studied and the results were compared with that obtained with CMPO-TBP in n-doddecane (n-DD). The distribution ratio of 241Am(III) in TBP-CMPO/bmimNTf2 was measured as a function of various parameters such as concentrations of nitric acid, CMPO, bmimNO3, NaNO3 and TBP and temperature. Remarkably large distribution ratios were observed for the extraction of americium(III) when bmimNTf2 acted as diluent and the extraction was insignificant in the absence of CMPO. The stoichiometry of metal–solvate in organic phase was determined by the slope analysis of extraction data and it indicated the formation of 1:3 (Am:CMPO) complex in organic phase. Viscosity of TBP-CMPO/bmimNTf2 at various temperatures and enthalpy change accompanied by the extraction of americium(III) were determined and reported in this paper.
{"title":"Extraction of americium(III) from nitric acid medium by CMPO-TBP extractants in ionic liquid diluent","authors":"A. Rout, K. Venkatesan, T. Srinivasan, P. Vasudeva Rao","doi":"10.1524/RACT.2009.1975","DOIUrl":"https://doi.org/10.1524/RACT.2009.1975","url":null,"abstract":"Abstract Extraction of americium(III) from nitric acid medium by a solution of tri-n-butylphosphate (TBP) and n-octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (CMPO) in room temperature ionic liquid, 1-butyl-3-methylimidazolium bis(trifluoromethanesulfonyl)imide (bmimNTf2), was studied and the results were compared with that obtained with CMPO-TBP in n-doddecane (n-DD). The distribution ratio of 241Am(III) in TBP-CMPO/bmimNTf2 was measured as a function of various parameters such as concentrations of nitric acid, CMPO, bmimNO3, NaNO3 and TBP and temperature. Remarkably large distribution ratios were observed for the extraction of americium(III) when bmimNTf2 acted as diluent and the extraction was insignificant in the absence of CMPO. The stoichiometry of metal–solvate in organic phase was determined by the slope analysis of extraction data and it indicated the formation of 1:3 (Am:CMPO) complex in organic phase. Viscosity of TBP-CMPO/bmimNTf2 at various temperatures and enthalpy change accompanied by the extraction of americium(III) were determined and reported in this paper.","PeriodicalId":21029,"journal":{"name":"Radiochimica Acta Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2009-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"78844327","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
P. Bienvenu, L. Ferreux, G. Andreoletti, N. Arnal, M. Lépy, M. Bé
Abstract A new value of 126Sn half-life was determined by combination of inductively coupled plasma-mass spectrometry (ICP-MS) and gamma spectrometry measurements on purified sample solutions collected from nuclear fuel reprocessing. 126Sn was isolated through dissolution of fission product precipitates and liquid-liquid extraction with N-benzoyl-N-phenyl-hydroxylamine (BPHA). The abundance of 126Sn atoms together with the absence of interfering species in the analysed solutions made it possible to measure both mass concentration and nuclide activity with high precision and accuracy. This led to a 126Sn half-life value of 1.980(57)×105 a.
摘要采用电感耦合等离子体质谱法(ICP-MS)和伽马谱法对核燃料后处理的纯化样品溶液测定了新的126Sn半衰期。126Sn通过裂变产物沉淀溶解和n -苯甲酰- n -苯基-羟胺(BPHA)液液萃取分离得到。在分析的溶液中，126Sn原子的丰度以及干扰物质的缺失使得测量质量浓度和核素活性具有很高的精度和准确性。这导致126Sn的半衰期值为1.980(57)×105 a。
{"title":"Determination of 126Sn half-life from ICP-MS and gamma spectrometry measurements","authors":"P. Bienvenu, L. Ferreux, G. Andreoletti, N. Arnal, M. Lépy, M. Bé","doi":"10.1524/RACT.2009.1673","DOIUrl":"https://doi.org/10.1524/RACT.2009.1673","url":null,"abstract":"Abstract A new value of 126Sn half-life was determined by combination of inductively coupled plasma-mass spectrometry (ICP-MS) and gamma spectrometry measurements on purified sample solutions collected from nuclear fuel reprocessing. 126Sn was isolated through dissolution of fission product precipitates and liquid-liquid extraction with N-benzoyl-N-phenyl-hydroxylamine (BPHA). The abundance of 126Sn atoms together with the absence of interfering species in the analysed solutions made it possible to measure both mass concentration and nuclide activity with high precision and accuracy. This led to a 126Sn half-life value of 1.980(57)×105 a.","PeriodicalId":21029,"journal":{"name":"Radiochimica Acta Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2009-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"85739166","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Abstract Nine samples of chewing tobacco, snuff, tobacco leaf and ash were analyzed using Instrumental Neutron Activation Analysis (INAA) and Atomic Absorption Spectroscopy (AAS). Almost all samples of chewing tobacco and snuff studied in this work contain substantial amounts of Mg, Mn, Na, K, V, Sc, Rb and Fe. Furthermore, varying amounts of Al, Ba, Ca, Ce, Co and Zn were also detected in all tobacco samples. Of the toxic elements which were determined using INAA, As, Sb and Hg were quantified in only few tobacco samples. However, other toxic elements, which were determined using AAS, such as Cu, Pb and Cd were detected in almost all samples of chewing tobacco and snuff. The concentration of majority of the detected elements is high in ash samples which imply that most elements in chewing tobacco and snuff may originate from the addition of ash.
{"title":"Evaluation of trace elements in chewing tobacco and snuff using instrumental neutron activation analysis (INAA) and atomic absorption spectroscopy (AAS)","authors":"S. Waheed, N. Siddique, S. Rahman","doi":"10.1524/RACT.2009.1672","DOIUrl":"https://doi.org/10.1524/RACT.2009.1672","url":null,"abstract":"Abstract Nine samples of chewing tobacco, snuff, tobacco leaf and ash were analyzed using Instrumental Neutron Activation Analysis (INAA) and Atomic Absorption Spectroscopy (AAS). Almost all samples of chewing tobacco and snuff studied in this work contain substantial amounts of Mg, Mn, Na, K, V, Sc, Rb and Fe. Furthermore, varying amounts of Al, Ba, Ca, Ce, Co and Zn were also detected in all tobacco samples. Of the toxic elements which were determined using INAA, As, Sb and Hg were quantified in only few tobacco samples. However, other toxic elements, which were determined using AAS, such as Cu, Pb and Cd were detected in almost all samples of chewing tobacco and snuff. The concentration of majority of the detected elements is high in ash samples which imply that most elements in chewing tobacco and snuff may originate from the addition of ash.","PeriodicalId":21029,"journal":{"name":"Radiochimica Acta Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2009-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"78923716","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
B. Brendebach, N. Banik, C. Marquardt, J. Rothe, M. Denecke, H. Geckeis
Abstract We perform X-ray absorption spectroscopy (XAS) investigations to monitor the stabilization of redox sensitive trivalent and tetravalent actinide ions in solution at acidic conditions in a pH range from 0 to 3 after treatment with holding reductants, hydroxylamine hydrochloride (NH2OHHCl) and Rongalite (sodium hydroxymethanesulfinate, CH3NaO3S). X-ray absorption near edge structure (XANES) measurements clearly demonstrate the stability of the actinide species for several hours under the given experimental conditions. Hence, structural parameters can be accurately derived by extended X-ray absorption fine structure (EXAFS) investigations. The coordination structure of oxygen atoms belonging to water ligands surrounding the actinide ions does not change with increasing pH value (approximately 11 O atoms at 2.42 Å in the case of U(IV) at pH 1, 9 O atoms at 2.52 Å for Np(III) at pH 1.5, and 10 O atoms at 2.49 Å for Pu(III) up to pH 3), indicating that hydrolysis reactions are suppressed under the given chemical conditions.
{"title":"X-ray absorption spectroscopic study of trivalent and tetravalent actinides in solution at varying pH values","authors":"B. Brendebach, N. Banik, C. Marquardt, J. Rothe, M. Denecke, H. Geckeis","doi":"10.1524/RACT.2009.1674","DOIUrl":"https://doi.org/10.1524/RACT.2009.1674","url":null,"abstract":"Abstract We perform X-ray absorption spectroscopy (XAS) investigations to monitor the stabilization of redox sensitive trivalent and tetravalent actinide ions in solution at acidic conditions in a pH range from 0 to 3 after treatment with holding reductants, hydroxylamine hydrochloride (NH2OHHCl) and Rongalite (sodium hydroxymethanesulfinate, CH3NaO3S). X-ray absorption near edge structure (XANES) measurements clearly demonstrate the stability of the actinide species for several hours under the given experimental conditions. Hence, structural parameters can be accurately derived by extended X-ray absorption fine structure (EXAFS) investigations. The coordination structure of oxygen atoms belonging to water ligands surrounding the actinide ions does not change with increasing pH value (approximately 11 O atoms at 2.42 Å in the case of U(IV) at pH 1, 9 O atoms at 2.52 Å for Np(III) at pH 1.5, and 10 O atoms at 2.49 Å for Pu(III) up to pH 3), indicating that hydrolysis reactions are suppressed under the given chemical conditions.","PeriodicalId":21029,"journal":{"name":"Radiochimica Acta Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2009-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"88875776","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
J. Kozempel, M. Hrubý, M. Nováková, J. Kučka, L. Lešetický, O. Lebeda
Abstract We describe a preparation of novel polymer vectors of 64Cu based on co-polymers of poly- (N-isopropylacrylamide) and poly- (N-hydroxypropylmethacrylamide). DOTA, DTPA, dipicolylamine, thiosemicarbazone and Ag-ionophore-II ligands were tested to bind 64Cu in a polymer chain. Labeling yields with no-carrier-added 64Cu varied from 95 to 99% in 30 min. at laboratory temperature. Vectors were stable in vitro for 24 h in human serum and might be prospective for targeted 64Cu radio or combined radiochemotherapy.
{"title":"Novel polymer vectors of 64Cu","authors":"J. Kozempel, M. Hrubý, M. Nováková, J. Kučka, L. Lešetický, O. Lebeda","doi":"10.1524/RACT.2009.1669","DOIUrl":"https://doi.org/10.1524/RACT.2009.1669","url":null,"abstract":"Abstract We describe a preparation of novel polymer vectors of 64Cu based on co-polymers of poly- (N-isopropylacrylamide) and poly- (N-hydroxypropylmethacrylamide). DOTA, DTPA, dipicolylamine, thiosemicarbazone and Ag-ionophore-II ligands were tested to bind 64Cu in a polymer chain. Labeling yields with no-carrier-added 64Cu varied from 95 to 99% in 30 min. at laboratory temperature. Vectors were stable in vitro for 24 h in human serum and might be prospective for targeted 64Cu radio or combined radiochemotherapy.","PeriodicalId":21029,"journal":{"name":"Radiochimica Acta Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2009-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"85898690","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Abmel Xiques Castillo, Keila Isaac Olivé, Edgar Casanova González, Denis Beckford, R. Leyva Montaña, A. Montero Álvarez, Eunice Olivé Álvarez
Abstract There is an increasing interest for 90Y for radionuclide therapy. However, radioimmunotherapy, one of the most important applications for 90Y, demands a very high purity product. Obtaining a high quality 90Y is difficult not only because of the complex and time consuming production schemes but also because of the quality control which has challenging tasks like the determination of 90Sr at very low concentrations. The present paper investigates a reported purification procedure for the removal of stable metal trace contaminants from an 90Y solution, seeking for its potential use in the elimination of the radioactive contaminant 90Sr and its fast determination. For this purpose a washing step with HNO3 acid is introduced to elute 90Sr, the order of each acid solution is rearranged to reduce the potential contaminants present in acids and the size of the column is reduced to further optimize the procedure. As a result, an improved purification method is obtained, which allows the removal of both trace metal contaminants and 90Sr from an 90Y solution and the measurement of 90Sr/90Y ratios of the order of 10-7, which are well below the established pharmacopeia limit of 2×10-5.
{"title":"An adapted purification procedure to improve the quality of 90Y for clinical use","authors":"Abmel Xiques Castillo, Keila Isaac Olivé, Edgar Casanova González, Denis Beckford, R. Leyva Montaña, A. Montero Álvarez, Eunice Olivé Álvarez","doi":"10.1524/RACT.2009.1666","DOIUrl":"https://doi.org/10.1524/RACT.2009.1666","url":null,"abstract":"Abstract There is an increasing interest for 90Y for radionuclide therapy. However, radioimmunotherapy, one of the most important applications for 90Y, demands a very high purity product. Obtaining a high quality 90Y is difficult not only because of the complex and time consuming production schemes but also because of the quality control which has challenging tasks like the determination of 90Sr at very low concentrations. The present paper investigates a reported purification procedure for the removal of stable metal trace contaminants from an 90Y solution, seeking for its potential use in the elimination of the radioactive contaminant 90Sr and its fast determination. For this purpose a washing step with HNO3 acid is introduced to elute 90Sr, the order of each acid solution is rearranged to reduce the potential contaminants present in acids and the size of the column is reduced to further optimize the procedure. As a result, an improved purification method is obtained, which allows the removal of both trace metal contaminants and 90Sr from an 90Y solution and the measurement of 90Sr/90Y ratios of the order of 10-7, which are well below the established pharmacopeia limit of 2×10-5.","PeriodicalId":21029,"journal":{"name":"Radiochimica Acta Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2009-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"77147134","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Abstract In this study, densely crosslinked poly(methacrylic acid) was used to adsorb uranium(VI) ions from aqueous solution. For this purpose, the crosslinked copolymer of ethylene glycol dimethacrylate (EGDM) and methacrylic acid (MA) containing 25% (w/w) methacrylic acid (MA) was synthesized by using dibenzoyl peroxide-N,N-dimethylaniline (BPO-DMA) initiator system at room temperature. The adsorption of uranium(VI) ions on the copolymer sample (0.02 g copolymer/5 mL solution of U(VI) ions) was carried out in a batch reactor. The parameters which effect the uranium adsorption process, such as, contact time, pH of solution, initial uranium(VI) concentration and temperature were investigated. It was observed that an increase in these parameters enhanced the removal of U(VI) ions from aqueous solution. The adsorption data were modelled by the Freundlich, Langmuir and Dubinin–Radushkevich (D–R) isotherms. The adsorption capacity of the crosslinked copolymer and free energy change were calculated by using D–R isotherms. Thermodynamic parameters (ΔH°, ΔS° and ΔG°) were determined for the adsorption of U(VI) ions from aqueous solutions by the crosslinked copolymer bearing methacrylic acid functional groups. Experimental adsorption data were analyzed using sorption kinetic models of the pseudo-first order and pseudo-second order kinetic models. It was observed that pseudo-second order kinetic model provided a high goodness of fit with experimental data for the adsorption of U(VI) ions on the crosslinked copolymer bearing methacrylic acid functional groups. The densely crosslinked poly(methacrylic acid) might be of interest in large scale uranium removals from aqueous solution, since it had high uranyl sorption capacities ranging from 0.16 mmol/g to 2.37 mmol/g copolymer at pH 2.7 (293 K).
摘要采用密交联聚甲基丙烯酸吸附水溶液中的铀(VI)离子。为此，采用过氧化二苯甲酰- n, n -二甲苯胺(BPO-DMA)引发剂体系，在室温下合成了含25% (w/w)甲基丙烯酸(MA)的乙二醇二甲基丙烯酸酯(EGDM)与甲基丙烯酸(MA)交联共聚物。在间歇反应器中进行了铀(VI)离子在共聚物样品(0.02 g共聚物/5 mL U(VI)离子溶液)上的吸附。考察了接触时间、溶液pH、初始铀浓度和温度等参数对铀吸附过程的影响。结果表明，这些参数的增加对U(VI)离子的去除率提高。吸附数据采用Freundlich、Langmuir和Dubinin-Radushkevich (D-R)等温线建模。用D-R等温线计算了交联共聚物的吸附量和自由能变化。测定了含甲基丙烯酸官能团的交联共聚物从水溶液中吸附U(VI)离子的热力学参数(ΔH°，ΔS°和ΔG°)。采用拟一级和拟二级吸附动力学模型对实验吸附数据进行了分析。结果表明，含甲基丙烯酸官能团的交联共聚物吸附U(VI)离子的拟二级动力学模型与实验数据拟合度较高。密交联聚(甲基丙烯酸)可能对从水溶液中大规模去除铀感兴趣，因为它在pH 2.7 (293 K)下具有高的铀酰吸附能力，范围为0.16 mmol/g至2.37 mmol/g共聚物。
{"title":"Kinetic and thermodynamic studies on the adsorption of U(VI) ions on densely crosslinked poly(methacrylic acid) from aqueous solutions","authors":"C. Özeroğlu, G. Keçeli","doi":"10.1524/RACT.2009.1668","DOIUrl":"https://doi.org/10.1524/RACT.2009.1668","url":null,"abstract":"Abstract In this study, densely crosslinked poly(methacrylic acid) was used to adsorb uranium(VI) ions from aqueous solution. For this purpose, the crosslinked copolymer of ethylene glycol dimethacrylate (EGDM) and methacrylic acid (MA) containing 25% (w/w) methacrylic acid (MA) was synthesized by using dibenzoyl peroxide-N,N-dimethylaniline (BPO-DMA) initiator system at room temperature. The adsorption of uranium(VI) ions on the copolymer sample (0.02 g copolymer/5 mL solution of U(VI) ions) was carried out in a batch reactor. The parameters which effect the uranium adsorption process, such as, contact time, pH of solution, initial uranium(VI) concentration and temperature were investigated. It was observed that an increase in these parameters enhanced the removal of U(VI) ions from aqueous solution. The adsorption data were modelled by the Freundlich, Langmuir and Dubinin–Radushkevich (D–R) isotherms. The adsorption capacity of the crosslinked copolymer and free energy change were calculated by using D–R isotherms. Thermodynamic parameters (ΔH°, ΔS° and ΔG°) were determined for the adsorption of U(VI) ions from aqueous solutions by the crosslinked copolymer bearing methacrylic acid functional groups. Experimental adsorption data were analyzed using sorption kinetic models of the pseudo-first order and pseudo-second order kinetic models. It was observed that pseudo-second order kinetic model provided a high goodness of fit with experimental data for the adsorption of U(VI) ions on the crosslinked copolymer bearing methacrylic acid functional groups. The densely crosslinked poly(methacrylic acid) might be of interest in large scale uranium removals from aqueous solution, since it had high uranyl sorption capacities ranging from 0.16 mmol/g to 2.37 mmol/g copolymer at pH 2.7 (293 K).","PeriodicalId":21029,"journal":{"name":"Radiochimica Acta Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2009-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"85546813","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Abstract Proton rich Tc radionuclides have been produced for the first time through 89Y(9Be, xn)93,94,95Tc reactions. In order to optimize the yield of a particular radionuclide of choice, batch yield of 93Tc, 94Tc and 95Tc have been measured at different incident energies using stacked-foil technique followed by off-line γ-spectrometry. No-carrier-added (nca) 93,94,95Tc radionuclides have been separated from bulk yttrium by liquid–liquid extraction (LLX) and solid–liquid extraction (SLX) techniques. Trioctylamine (TOA) diluted in cyclohexane was used as liquid anion exchanger in LLX in presence of HCl. SLX was carried out using cation and anion exchanger resin, DOWEX-50 and DOWEX-1, respectively, in HCl medium.
{"title":"Production and separation of no-carrier-added 93,94,95Tc from 9Be activated yttrium target","authors":"M. Maiti, S. Lahiri","doi":"10.1524/RACT.2009.1667","DOIUrl":"https://doi.org/10.1524/RACT.2009.1667","url":null,"abstract":"Abstract Proton rich Tc radionuclides have been produced for the first time through 89Y(9Be, xn)93,94,95Tc reactions. In order to optimize the yield of a particular radionuclide of choice, batch yield of 93Tc, 94Tc and 95Tc have been measured at different incident energies using stacked-foil technique followed by off-line γ-spectrometry. No-carrier-added (nca) 93,94,95Tc radionuclides have been separated from bulk yttrium by liquid–liquid extraction (LLX) and solid–liquid extraction (SLX) techniques. Trioctylamine (TOA) diluted in cyclohexane was used as liquid anion exchanger in LLX in presence of HCl. SLX was carried out using cation and anion exchanger resin, DOWEX-50 and DOWEX-1, respectively, in HCl medium.","PeriodicalId":21029,"journal":{"name":"Radiochimica Acta Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2009-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"87938670","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Abstract Effects of different diluents on the extraction of cobalt(II) and indium(III) oxinate complexes have been studied using Co-60 and In-114m as radiotracers. Theory of regular solutions was applied for the determination of solubility parameters (δ) of cobalt oxinate and indium oxinate which were found to be 34.45 J1/2cm-3/2 and 34.03 J1/2 cm-3/2, respectively. Besides, distribution of each of the two complexes was studied in the mixtures of two solvents, assigned as good and poor solvents, in accordance with their individual behaviors. In both of the two cases, experimentally determined values of distribution-coefficient differed from those of calculated values which shows the importance of solute-solvent and solvent-solvent interaction in the present system.
{"title":"Determination of solubility parameters of cobalt(II) and indium(III) oxinates by tracer technique","authors":"M. Mandal, R. Sarkar (Sain), S. Basu","doi":"10.1524/RACT.2009.1665","DOIUrl":"https://doi.org/10.1524/RACT.2009.1665","url":null,"abstract":"Abstract Effects of different diluents on the extraction of cobalt(II) and indium(III) oxinate complexes have been studied using Co-60 and In-114m as radiotracers. Theory of regular solutions was applied for the determination of solubility parameters (δ) of cobalt oxinate and indium oxinate which were found to be 34.45 J1/2cm-3/2 and 34.03 J1/2 cm-3/2, respectively. Besides, distribution of each of the two complexes was studied in the mixtures of two solvents, assigned as good and poor solvents, in accordance with their individual behaviors. In both of the two cases, experimentally determined values of distribution-coefficient differed from those of calculated values which shows the importance of solute-solvent and solvent-solvent interaction in the present system.","PeriodicalId":21029,"journal":{"name":"Radiochimica Acta Radiochimica Acta","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2009-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"91337558","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
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