共查询到20条相似文献,搜索用时 15 毫秒
1.
L. I. Guseva 《Journal of Radioanalytical and Nuclear Chemistry》2007,272(1):153-159
A new tandem generator system (cation-exchange generator column coupled to anion-exchange), based on the 228Ra as starting radionuclide, for 212Pb/212Bi production in the solutions suitable to direct application in biomedical investigations has been developed. Optimum conditions
have been found for retention of Ra, Th and Ac parent radionuclides on the cation-exchange column and repeated elution of
Pb with subsequent concentration on anion-exchange column using HBr and mixed HBr/CH3OH solutions. It was shown that Pb/Bi could be eluted from anion — exchange column with a small volume of EDTA, DTPA, NaCl
solutions or heated H2O. The advantages of the tandem generator system for production of short-lived Pb/Bi radionuclides and their application for
biomedical studies are discussed. 相似文献
2.
Fast radiochemical separation of carrier-free212Pb–212Bi–208Tl in radioactive equilibrium was performed using the HPLC technique with an ion-exchange column /ION-210 for cation exchange, ION-110 for anion exchange and C18 loaded with cation-exchange sites/. Optimal results are obtained with the ION-110 column.208Tl and212Pb are eluted by 0.5M HCl in 2.5 and 5 min, respectively.212Bi is recovered by elution with 1M HNO3. 相似文献
3.
Andrey G. Kazakov Taisya Y. Ekatova Julia S. Babenya Sergey S. Belyshev Vadim V. Khankin Alexander A. Kuznetsov Sergey E. Vinokurov Boris F. Myasoedov 《Molecules (Basel, Switzerland)》2022,27(10)
A new method of production of one of the most widely used isotopes in nuclear medicine, 177Lu, with high chemical purity was developed; this method includes irradiation of the HfO2 target with bremsstrahlung photons. The irradiated target was dissolved in HF and then diluted and placed onto a column filled with LN resin. Quantitative sorption of 177Lu could be observed during this process. The column later was rinsed with the mixture of 0.1 M HF and 1 M HNO3 and then 2 M HNO3 to remove impurities. Quantitative desorption of 177Lu was achieved by using 6 M HNO3. The developed method of 177Lu production ensures high purification of this isotope from macroquantities of hafnium and zirconium and radioactive impurities of carrier-free yttrium. The content of 177mLu in 177Lu in photonuclear production was determined. Due to high chemical and radionuclide purity, 177Lu obtained by the developed method can be used in nuclear medicine. 相似文献
4.
M. Yarmohammadi M. Mirzaii M. Sadeghi 《Journal of Radioanalytical and Nuclear Chemistry》2013,295(2):987-990
A radiochemical purification procedure was developed for the separation of enriched cadmium (111Cd and 112Cd) from natural copper that used as backing; and was based upon the chromatographic adsorption. The separation of copper from cadmium was studied in this work. The ions were selectively separated from aqueous solution. Ion-exchange chromatography was employed as a column (1.5 cm i.d. and 15 cm length) with AG1-X8 resin (chloride form, 100–200 mesh) and a flow rate of 1–2 ml/min throughout the separation. 6 M HCl media was used for the adsorption of Cd and Cu on the resin. Then, Cu was eluted by 2 M HCl and Cd by 100 ml 0.5 M HNO3. The amount of Cu and Cd ions in the final solution (0.5 M HNO3) were measured by pulse polarographic method and the concentration of Cu was found to be <0.1 ppm. The Cd was quantitatively recovered and the recovery yield from ion-exchange chromatography was greater than 96 %. 相似文献
5.
A. Bhattacharyya P. K. Mohapatra P. N. Pathak V. K. Manchanda 《Journal of Radioanalytical and Nuclear Chemistry》2006,268(2):323-328
Summary Sorption
behavior of Th and U on cation-exchange resins was investigated from nitric
acid medium by both batch and column methods. The cation-exchange studies
involved the sorption of UO22+ and Th4+ and
their cationic complexes onto Dowex 50Wx8 and Dowex 50Wx4 resins (50-100 mesh).
The batch data yielded a separation factor (Kd,Th/Kd,U)
value of >100 for the cation-exchanger, Dowex 50Wx4 at 1-2M HNO3.
Separation of uranium from thorium was also carried out by column method in
nitric acid medium using cation-exchangers, Dowex 50Wx4 as well as Dowex 50Wx8.
While uranium elution was possible at 1M HNO3, Th could be eluted
only at higher concentration of nitric acid (>6M). The stripped solution
emanating from a mixer settler employing di-2-ethyl hexyl isobutyramide as
extractant and feed solution similar to THOREX process comprising 350 mg/l U
and 380 mg/l Th in 0.75M HNO3 was loaded on the column and the
decontamination factor value for U in the product was >1000.</p>
</p> 相似文献
6.
L. I. Guseva G. S. Tikhomirova N. N. Dogadkin 《Journal of Radioanalytical and Nuclear Chemistry》2004,260(1):167-172
A simple and effective method has been developed for the continuous production of the short-lived isotope Pb as a homolog
of element 114 on the principle of a radionuclide generator. The method is based on the initial sorption of 227Ac or 223Ra on a small cation-exchange column, with subsequent “milking” of 211Pb (36.1 m) by a mixture of HCl/CH3OH. The optimum conditions for the repeated separation of 211Pb from radionuclides strongly sorbed by the cation-exchanger (Ac, Th, Ra, Pu, TPE) have been determined. Possibilities of
using the 211Pb generator for test experiments on the solution chemistry of element 114 have been shown. Advantages of aqueous alcohol
HCl solutions for the isolation of 211Pb (element 114) are discussed.
This revised version was published online in August 2006 with corrections to the Cover Date. 相似文献
7.
S. Al Waér B. Al Medehem V. F. Peretrukhin 《Journal of Radioanalytical and Nuclear Chemistry》1987,116(2):253-260
A two-step chromatographic technique was elaborated to isolate144Ce,144Pr from a solution of uranium fission products in 6M HNO3. The oxidation to Ce(III) by bromate and selective adsorption of144Ce(IV) on anion exchange column were used to concentrate and purify144Ce. Some impurities of uranium,95Zr,95Nb,106Ru remain in144Ce solution after the first step of its isolation. The final purification is achieved by passing the 6M HNO3 solution of144Ce(IV) through the HDEHP-coated teflon column. The decontamination factors of144Ce from main fission products are given. 7.2 mCi of (144Ce+144Pr) are recovered from each gram of irradiated uranium trioxide with the yield greater than 99%. An improvement of known generator was carried out to elute a purer144Pr from maternal144Ce(IV) adsorbed on the anion exchange column. 相似文献
8.
Radiochemical separations of carrier-free210Bi and UX1 activities from210Pb and U, respectively, have been carried out using a silica gel column.210Pb was adsorbed in the column as molybdate and210Bi passed unadsorbed. Lead activity was next removed with 25 ml of 0.1 M HNO3. In the case of separation of UX1, the coloured carbonate complex of U was removed from the silica surface by washing with saturated sodium carbonate solution,
keeping UX1 retained, and finally UX1 was washed out with 25 ml of conc. HNO3. Studies of the beta decay of210Bi and the γ-spectrum analysis of UX1 has shown that the separated products in both cases are of high radiochemical purity. The processes in each case took less
than one hour and the yield was satisfactory. 相似文献
9.
Moumita Maiti Kaustab Ghosh Susanta Lahiri 《Journal of Radioanalytical and Nuclear Chemistry》2013,295(3):1945-1950
A natural silver foil was bombarded by 30 MeV α-particles which produced 111In, 109Cd and 106mAg in the target matrix. 111In and 109Cd were separated from the Ag target matrix employing ion-exchange chromatography and liquid–liquid extraction (LLX). In the chromatographic separation, the active solution containing the NCA products were adsorbed in the column containing Dowex 50 and were eluted with HNO3. Bulk silver and 109Cd were sequentially eluted with 1 M HNO3. After complete elution of 109Cd and the bulk, 111In was eluted with 1.5 M HNO3. In the LLX, the NCA 111In was extracted to 1 % HDEHP (di-2(ethylhexyl)phosphoric acid) from 10?2 M HNO3 solution, leaving cadmium and bulk silver quantitatively in the aqueous phase. The NCA 109Cd was separated from the bulk Ag by precipitating Ag as AgCl. NCA 111In was stripped back quantitatively from HDEHP phase using 8 M HNO3. 相似文献
10.
Separation method of Zr using trans uranium resin (TRU resin) and tetra valent actinide resin (TEVA resin) was developed for the analysis of 93Zr contained in the rubble waste. Zr, Nb, and U were quantitatively extracted on the TRU resin from 3 M HNO3 and striped with 0.01 M HF, in addition, some part of Mo, Hg, Bi, and Th were also included in the stripping solution. The stripping solution was evaporated to eliminate HNO3 and the residue was dissolved in 0.1 M HF. Finally, Zr was separated from Nb and Mo with the TEVA resin. 相似文献
11.
M. A. El-Absy M. A. El-Amir T. W. Fasih H. E. Ramadan M. F. El-Shahat 《Journal of Radioanalytical and Nuclear Chemistry》2014,299(3):1859-1864
In this work alumina 99Mo-molybdate (VI) gel is evaluated as a column matrix for use in the preparation of small chromatographic column type 99mTc generator. Alumina molybdate (VI) gel is prepared by dissolving inactive MoO3 with aluminum foil in 5 M NaOH solution containing 99Mo radiotracer. After complete dissolution, 0.5 H2O2 was added to the reaction mixture solution and acidified to pH 5.5 with concentrated HNO3. The formed AlMo precipitate was washed with NaNO3 solution, dried at 50 °C for 24 h and then packed in the form of a chromatographic column for elution of the generated 99mTc radionuclide with physiological saline solution (0.9 % NaCl). Greater than 86 % of the generated 99mTc activity is immediately and reproducibly eluted with passing 10 mL of the saline solution through 2.0 g of alumina 99Mo-molybdate column bed at a flow rate of about 1.0 mL/min. The high radiochemical ≥98.6 % TcO4 ?, radionuclidic ≥99.90 % 99mTc and chemical purities of the eluates satisfy the specifications for use in nuclear medicine. 相似文献
12.
Barbara Bartoś Krzysztof Lyczko Agata Kasperek Seweryn Krajewski Aleksander Bilewicz 《Journal of Radioanalytical and Nuclear Chemistry》2013,295(1):205-209
The short half-life of 212Bi and 213Bi limits the application of these radionuclides in α radionuclide therapy. The labeling of biomolecules with 212Pb (mother nuclide of 212Bi) instead of 212Bi or 213Bi has the advantage of obtaining a conjugate with a half-life of 10.6 h, compared with of 60 min for 212Bi or 46 min for 213Bi. Previous attempts to prepare a potential in vivo generator with 212Pb complexed by the DOTA chelator failed, because about 36 % of Bi was reported to escape as a result of the radioactive decay $^{{212}}{\text{Pb}}{\mathop{\longrightarrow}\limits^{\beta ^{ - }}}{^{212}{\text{Bi}}}$ . Herein, we report studies on the stability of the 212Pb complexes with eight selected polydentate ligands, which demonstrate high affinity for 3+ metal cations. From the ligand studied DOTP and BAPTA show a sufficient 212Pb labeling yields but only 212Pb–DOTP complex is stable in isotonic solution of sodium chloride making this way radioactivity level of released 212Bi is below the limit of detection. It should be emphasized that the DOTP complex is stable only in the case when the concentration of free DOTP exceeds 10?4 M. 相似文献
13.
《Analytical letters》2012,45(10):1821-1834
In this study 4-chloro-7-nitrobenzo-2-oxa-1,3-diazole (NBD-Cl) is proposed as a post-column derivatization (PCD) reagent for the fluorescence detection of aliphatic primary and secondary amines after HPLC separation. Five primary (methylamine, isoamylamine, 2-phenylethylamine, putrescine, and histamine) and one secondary amine (dimethylamine) were separated isocratically on a cation-exchange column using HNO3 (5 × 10?3 mol L?1) as the mobile phase. Post-column derivatization was based on two steps: 1) the derivatization of amines with NBD-Cl in alkaline medium, and 2) the acidification of the resulted mixture in order to minimize the background signal of the reagent and improve dramatically the sensitivity and determination range. The variables of the post-column reaction (concentration of NBD-Cl, buffer concentration and pH, reaction temperature, concentration of HCl, flow rates of the reagents) were thoroughly investigated. Critical chromatographic parameters such as the concentration of HNO3, the percentage of organic solvent, and the column temperature were also examined to achieve adequate separation. An internal standard of 1,7-diaminoheptane was used. The developed post-column method provides the ability for a fully automated analysis, low detection limits (LODs 20–100 µg L?1 with S/N = 3), and it requires less sample preparation. The applicability of the proposed analytical scheme was demonstrated by the determination of histamine (HIS) in tuna fish tissues according to US Food and Drug Administration (FDA) guidelines. 相似文献
14.
Guogang Jia 《Journal of Radioanalytical and Nuclear Chemistry》2017,311(2):1007-1017
In the method, soil was fused together with Na2CO3 and Na2O2 at 600 °C, uranium and thorium were leached out with HCl, HNO3 and HF, and HClO4 was used to eliminate the residual HF through evaporation. The leaching solution (2 M HNO3) was passed through a Microthene-TOPO column to adsorb uranium and thorium. Thorium was first eluted with 2 M HCl and electrodeposited in 0.025 M H2C2O4 + 0.15 M HNO3 on a stainless steel disc. Uranium was eluted with a 0.025 M ammonium oxalate solution and also electrodeposited. Both thorium and uranium isotopes on the discs were measured separately by α-spectrometry. 相似文献
15.
An ion chromatography method is described for the simultaneous determination of anions (Cl–, NO3–, and SO42–) and cations (Na+, NH4+, K+, Mg2+, and Ca2+) using a single pump, a single eluent and a single detector. An anion-exchange column modified with chondroitin sulfate C facilitated the elution of the above three anions using 5 mM tartaric acid as the eluent in isocratic mode, whereas the same eluent facilitated the separation of the above five cations on a commercially-available cation-exchange column. The separation columns were connected in series via two six-port switching valves, so the required cation-exchange or anion-exchange separation could be carried out by selecting the appropriate positions for the switching valves. The separations were completed in 30 min. 相似文献
16.
M. Nogami Y. Sugiyama T. Kawasaki M. Harada Y. Kawata Y. Morita T. Kikuchi Y. Ikeda 《Journal of Radioanalytical and Nuclear Chemistry》2013,296(1):423-427
Polyvinylpolypyrrolidone (PVPP) is a resin with adsorption selectivity for U(VI) in HNO3 media. The stability of this resin has been examined against gamma-ray irradiation using HNO3 solutions of various concentrations. Samples of PVPP immersed in HNO3 solutions up to 6 mol·dm?3 (=M) were irradiated by a 60Co source at 3.6 kGy·h?1 to reach 0.90 MGy at room temperature under ambient atmosphere. As a result, no clear decrease in the capacity for U(VI) when added in 3 M HNO3 was observed for any samples, or rather the capacity was found to increase by approximately 50 % for PVPP irradiated in 6 M HNO3. It was indicated from some spectroscopic analyses of the irradiated samples that the irradiation causes the cleavage of the pyrrolidone ring of PVPP. This occurs by the addition of an oxygen atom originating from HNO3, followed by the formation of straight-chain groups with multiple coordinative atoms by the successive addition of oxygen, finally leading to the generation of a primary-amine-type weakly-basic anion exchange resin. The increase in the U(VI) capacity would be due to the formation of the straight-chain groups. However, such structural changes were not observed by heating at 323 K in up to 6 M HNO3 for 20 days. Thus, it was shown that PVPP is a heat-resistant resin. 相似文献
17.
A. Bartosova P. Rajec M. Reich 《Journal of Radioanalytical and Nuclear Chemistry》2004,261(1):119-124
An extraction chromatographic material based on Aliquat-336 anchored on hydrophobized silica gel support was prepared as an
ion exchanger. The prepared material appeared to be suitable for the separation of 99Tc from environmental matrices in column application. The properties of the material, sorption characteristic and distribution
coefficient of 99mTcO4
-in various media were studied. The prepared sorbent was conditioned by washing with nitric acid. The solution containing 99mTcO4
- in 0.1M HNO3 was passed through the column. Tc was eluted from the column by 8M HNO3. The flow rate was 0.4 ml/min. The chemical yield of technetium during the separation process was determined using 99mTc tracer and gamma measurement. The sorption recovery of Tc from the prepared sorbent with 0.1M HNO3 solution was more than 98%, and the desorption recovery from the column using 8M HNO3 varied between 92-96%. It was found that the prepared sorbent is suitable for the separation of technetium from environmental
matrices and radioactive wastes.
This revised version was published online in July 2006 with corrections to the Cover Date. 相似文献
18.
Shigeo Taguchi Masahiko Yamamoto Naoki Surugaya Akira Kurosawa Toshiaki Hiyama Tatsuhiko Tanaka 《Journal of Radioanalytical and Nuclear Chemistry》2011,288(2):435-441
A flow injection-based electrochemical detection system coupled to a solid-phase extraction column was developed for the determination of trace amounts of plutonium in low-active liquid wastes from spent nuclear-fuel reprocessing plants. The oxidation state of plutonium in a sample solution was adjusted to Pu(VI) by the addition of silver(II) oxide. A sample solution was made up in 3 mol L?1 HNO3 and loaded onto a column packed with UTEVA® with 3 mol L?1 HNO3 as the carrier. Plutonium(VI) was adsorbed onto the resin, and interfering elements were removed by rinsing the column with 3 mol L?1 HNO3. Subsequently, the adsorbed Pu(VI) was eluted with 0.01 mol L?1 HNO3, and then introduced directly into the flow-through electrolysis cell with boron-doped diamond electrode. The eluted Pu(VI) was detected by an electrochemical amperometric method at a working potential of 0.1 V (vs. Ag/AgCl). The current produced on reduction of Pu(VI) was continuously monitored and recorded. The plutonium concentration was calculated from the relationship between the peak area and concentration of plutonium. The relative standard deviation of ten analyses was 1.1% for a plutonium solution of 25 μg L?1 containing 50 ng of Pu. The detection limit calculated from three-times the standard deviation was 0.82 μg L?1 (1.6 ng of Pu). 相似文献
19.
Shigeo Taguchi Masahiko Yamamoto Naoki Surugaya 《Journal of Radioanalytical and Nuclear Chemistry》2014,299(3):1539-1545
In this study, a flow-based electrochemical detection system coupled to a solid-phase extraction column was developed for the determination of neptunium in the presence of Pu(IV). Np(V) in the sample solution was completely oxidized to Np(VI) via electrolysis using a column electrode composed of carbon fibers. The column electrode effluent was then loaded onto a TEVA® column, and subsequently onto a UTEVA® column using 3 mol L?1 HNO3. Pu(IV) was retained on the TEVA column and separated from Np(VI), while Np(VI) was retained on the UTEVA column. Np(VI) was eluted from the UTEVA column with 0.01 mol L?1 HNO3 and then introduced directly into a flow-through electrolysis cell. An electrochemical amperometric method with a working potential of +0.1 V (vs. Ag/AgCl) was used to detect Np(VI). The current produced due to the reduction of Np(VI) was continuously monitored and recorded, and the Np concentration was calculated from the peak area. The relative standard deviation of 10 analyses was 2.4 % for an Np solution (0.50 mg L?1) containing 1.0 μg Np. The detection limit, which was determined to be three times the standard deviation, was 35 μg L?1 (70 ng Np). 相似文献
20.
I. C. Pius M. M. Charyulu C. K. Sivaramakrishnan S. K. Patil 《Journal of Radioanalytical and Nuclear Chemistry》1994,187(1):57-65
Distribution ratios of Pu(IV) between 7.5M HNO3+0.75M H3PO4+0.3M H2SO4 media and a macroporous anion-exchange resin Amberlyst A-26 (MP) increased from 40 to 250 when 1M aluminium nitrate was added to the aqueous medium. When 1M ferric nitrate was used in place of aluminium nitrate the distribution ratio further increased to 850. The 10% Pu(IV) breakthrough capacities with a 5 ml bed resin column, using synthetic feed solutions containing 1M aluminium nitrate, were 1.4 g l–1, 3.2 g l–1 at flow rates of 30 ml per hour and 10 ml per hour, respectively. The corresponding 10% Pu(IV) breakthrough capacities in the presence of 1M ferric nitrate were 8.5 g l–1 and 12.8 g l–1. More than 97% of plutonium could be recovered from actual analytical phosphate waste solutions. 相似文献