共查询到20条相似文献,搜索用时 15 毫秒
1.
Le Van So P. Pellegrini A. Katsifis J. Howse I. Greguric 《Journal of Radioanalytical and Nuclear Chemistry》2008,277(2):451-466
The radiochemical separation of the different radionuclides (64Cu, 67Cu, 67Ga, 66Ga, 56Ni, 57Ni, 55Co, 56Co, 57Co, 65Zn, 196Au) induced in the Ni supported Cu substrate — 68Zn target system, which was bombarded with the 29.0 MeV proton beam, was performed by ion-exchange chromatography using successive
isocratic and/or concentration gradient elution techniques. The overlapped gamma-ray spectrum analysis method was developed
to assess the 67Ga and 67Cu content in the 64Cu product and even in the post-67Ga production 68Zn target solution without the support of radiochemical separation. This method was used for the assessment of 64+67Cu radioisotope separation from 67Ga, the quality control of 64Cu product and the determination of the 68Zn (p,2p)67Cu reaction yield. The improvement in the targetry and the optimization of proton beam energy for the 68Zn target based 64Cu and 67Ga production were proposed based on the stopping power and range of the incident proton and on the excitation functions,
reaction yields and different radionuclides induced in the target system. 相似文献
2.
M. M. Shehata B. Scholten I. Spahn H. H. Coenen S. M. Qaim 《Journal of Radioanalytical and Nuclear Chemistry》2011,287(2):435-442
A method for the separation of no-carrier-added arsenic radionuclides from the bulk amount of proton-irradiated GeO2 targets as well as from coproduced radiogallium was developed. The radionuclides 69Ge and 67Ga produced during irradiation of GeO2 were used as tracers for Ge and Ga in the experiments. After dissolution of the target the ratio of As(III) to As(V) was
determined via thin layer chromatography (TLC). The extraction of radioarsenic by different organic solvents from acid solutions
containing alkali iodide was studied and optimized. The influence of the concentration of various acids (HCl, HClO4, HNO3, HBr, H2SO4) as well as of KI was studied using cyclohexane. The optimum separation of radioarsenic was achieved using cyclohexane with
4.75 M HCl and 0.5 M KI and its back-extraction with a 0.1% H2O2 solution. The separation leads to high purity radioarsenic containing no radiogallium and <0.001% [69Ge]Ge. The overall radiochemical yield is 93 ± 3%. The practical application of the optimized procedure in the production
of 71As and 72As is demonstrated and batch yields achieved were in the range of 75–84% of the theoretical values. 相似文献
3.
M. A. El-Absy M. Mostafa M. A. El-Amir H. El-Said A. A. Abdel Fattah H. M. Aly 《Journal of Radioanalytical and Nuclear Chemistry》2005,267(1):161-167
Summary Barium-137m radioisotope generator of the chromatographic column elution mode based on loading 1.5 g 6-tungstocerate(IV) gel
matrix with ~54 kBq of fission-produced 137Cs is described. The elution performance of the generated 137mBa radionuclide was investigated as a function of chemical composition of the eluent, flow rate, elution frequency, and age
of the generator system. At comparable conditions, 137mBa eluates with 0.9% NaCl-0.1M HCl eluent had higher elution yields and radionuclidic purity than with 0.1M NH4Cl-0.1M HCl eluent. The generator has been repeatedly eluted for 311 days by passing 4810 ml of the saline eluent (10 ml ×
481 elution operations) at a flow rate of 3.0 ml/min. Barium-137m eluates of high and reproducible elution yields, chemical
and radionuclidic purities of (≥ 99.99%) were obtained. 相似文献
4.
Summary Iron separation is described from liquid samples with a high concentration of ions that enables simple determination of 55Fe. One of the described methods consists of iron precipitation from a large volume seawater by sodium hydroxide and/or ammonium
carbonate and separation from other elements (Ca, Sr, Cu, Mg, etc.) on a TRU column with 4M HCl or 8M HNO3. In the other procedure iron is separated directly from a mixture of seawater samples and HCl on a TRU column. In both methods,
the iron recovery is almost 100%. After separation, 55Fe is determined by counting with a liquid scintillation counter. The binding of Fe and Zn on TEVA, U/TEVA and TRU resins
from seawater solutions of HCl and HNO3depends on the type of the resin, concentration of acid and other ions. Iron and zinc can be separated from seawater on a
U/TEVA column with 2M HCl. 相似文献
5.
K. F. Allan M. M. S. Ali H. A. Hanafi K. M. El-Azony 《Journal of Radioanalytical and Nuclear Chemistry》2010,284(2):297-301
The activated carbon was prepared by using corncobs and characterized by sorpatometer for using as an exchanger material to
separate the generated 113mIn from 113Sn and 124,125Sb. To optimize the separation process, the different parameters like acetone percentage, HCl concentration were studied.
The exchange capacity of Sn(IV) is 7.6 meq/g onto the activated carbon and the elution efficiency of 113mIn > 80% by using 10 mL of 0.2 M HCl-80% acetone with flow rate 1 mL/min. The radionuclidic purity and radiochemical purity
of the eluted 113mIn were examined and clarified the presence of 124,125Sb with relatively high level as radio impurities, so further separation was carried out by using Dowex 1×8 as an anion exchanger
below the activated carbon matrix on the same separation column to adsorb the 113Sn and 124,125Sb, which escape from the activated carbon matrix. 相似文献
6.
M. A. Hassanein H. El-Said M. A. El-Amir 《Journal of Radioanalytical and Nuclear Chemistry》2006,269(1):75-80
Summary A procedure for the separation of 64,67Cu radioisotopes from irradiated natural zinc targets was developed. Production of 64,67Cu was carried out using 64,67Zn(n,p)64,67Cu reactions by fast neutron bombardment of natural zinc targets at The Second Egyptian Research Reactor (ETRR-2). The sorption
behavior of 65Zn and 64,67Cu ions in HCl acid solutions showed high affinity of Cu ions towards 6-tungstocerate(IV) gel matrix compared with Zn ions.
Carrier-free 64,67Cu radionuclides were separated from 65Zn on 6-tungstocerate(IV) column matrix by eluting the column with 10 ml 0.001 and 1M HCl acid solutions. The separated 64,67Cu radionuclides were of high chemical, radiochemical and radionuclidic purity. 相似文献
7.
K. Aardaneh K. Aardaneh K. Aardaneh T. N. van der Walt T. N. van der Walt T. N. van der Walt 《Journal of Radioanalytical and Nuclear Chemistry》2006,268(1):25-32
Summary The target for the production of68Geconsists of a disc of gallium suboxide, Ga2O, with a 19 mm diameter. The suboxide was primarily prepared by repeatedly mixing metallic Ga and Ga2O3at 700 °C. The target (2.4 g) was quite stable under a long-time irradiation with a 34 MeV proton beam at a current of ~80<span
lang=EN-ZA style='font-size:12.0pt; font-family:Symbol;mso-bidi-font-family:Symbol;mso-ansi-language:EN-ZA'>mA. The dissolution
of the target was performed using 12M sulphuric acid solution, assisted with the dropwise addition of 30% H2O2solution, and took less than 4 hours. A solvent extraction method, using a 9M H2SO4-0.3M HCl/CCl4system, was employed for the radiochemical separation of68Ge from Ga and Zn radionuclides, while 0.05M HCl was used for the back extraction of68Ge from the organic phase. The68Ge obtained in the dilute HCl was directly loaded onto a column containing either a hydrous tin dioxide or a crystalline tin
dioxide, obtained by calcinations of the hydrous oxide at 450, 700, and 900 °C. The calcinated hydrous tin dioxide at 900
°C showed the highest crystallinity and highest68Ga elution yield and was selected for use in the generator. The68Ga elution from the column generator packed with 2 g of tin dioxide, using 3 ml of 1M HCl, and yielded an average of 65%.
The breakthrough of68Ge was 6.1. 10-4%. 相似文献
8.
Summary An extraction chromatography method was developed for the separation of 239Np from 243Am in nitric acid solution. A sorbent based on aliphatic quaternary amine Aliquat-336 and hydrophobized silica gel was prepared. 239Np reduced to the oxidation state(IV) with ferrous sulfamate in 2M or 6M HNO3 sorbs on the prepared silica gel column. After washing with 0.1M ferrous sulfamate in 2.5M HNO3, 239Np is eluted with 0.1M HNO3 containing 0.02M HF. The separation of 243Am from 239Np is very effective. The purity of 239Np was found to be better than 99.5%. The proposed 239Np milking procedure is suitable for the preparation of 239Np tracer that can be used for the determination of 237Np radiochemical yield. 相似文献
9.
K. Aardaneh C. Naidoo G. F. Steyn 《Journal of Radioanalytical and Nuclear Chemistry》2008,276(3):831-834
A radiochemical separation method was developed for the separation of 109Cd from a nat.Ag target (6.6 g, pressed into a 19 mm disc). The method comprised of two stages. In the first stage, after dissolution of
the target in nitric acid, silver was separated from Cd by precipitation into the metallic form using 20 g of Cu turnings
for the reduction of Ag+ ions. In the second stage, 109Cd in the filtrate, that contained trace amount of silver and substantial quantity of Cu(I), was purified by use of a Bio-Rad
AG1-X10 anion-exchange resin. The ion-exchange chromatography employed a column with (1.6 cm i.d. and 4 cm length) with a
flow rate of 2 ml/min throughout the separation. 109Cd was quantitatively recovered from the first stage and the recovery yield from the ion-exchange chromatography was greater
than 96%. 2M HCl containing H2O2 was used for the adsorption of 109Cd and elution of Cu. 109Cd was eluted by 50 ml 1M HNO3. The concentrations of stable isotopes of Ag and Cu in the final solution (5 ml 0.05M HCl) were measured by an ICP-OES method
and found to be <1 ppm. 相似文献
10.
E. Roy Clark Kawther A. Al-Zubaidi H. Al-Shahristani 《Journal of Radioanalytical and Nuclear Chemistry》1980,60(1):149-158
The silica gel adsorption behaviour of zirconium, niobium, ruthenium and cerium in hydrochloric acid has been investigated
by batch and column techniques. A satisfactory radiochemical separation of zirconium and niobium from each other and from
other fission products has been achieved by a two column technique. The recommended procedure consists of sorption of all
the nuclides on a primary silica gel column. Fifteen per cent of95Nb, all of the zirconium and all of the other fission products are eluted first by washing with 5.5 M HCl. A second elution
with concentrated hydrochloric acid then recovers the95Nb (free from other products). The solution from the first elution after evaporation to 1 ml is then passed through another
silica gel column and successively washed with 0.5M HCl, 5.5M HCl and concentrated HCl to obtain three fractions—other fission
products—95Zr free from other products—95Nb free from other products, respectively. 相似文献
11.
H. El-Said A. A. El-Sadek M. I. Aydia K. M. El-Azony 《Journal of Radioanalytical and Nuclear Chemistry》2018,317(3):1341-1347
The zirconium silicotungstate (ZrSiW) was studied as an effective sorbent material to be used in the 113Sn/113mIn generator. The results elucidated that the distribution coefficient of 113Sn (3700 mL/g) is greater than 113mIn (275 mL/g) from 0.1 M HCl acid solution to the ZrSiW material. The maximum sorption capacity of Sn (IV) was found to be 33 mg per gram ZrSiW (~?0.3 mmol/g). The elution yield of 113mIn was found to be >?78?±?6.4% with an acceptable purity of radionuclidic and radiochemical (≥?99.99 and 96.8%, respectively). The rigorous separation of 113mIn from the 125Sb was carried out due to its long half-life (2.758 years) and beta emission that causes tissue damage. Zr, W and Si levels are below the permitted limit in the 113mIn eluate. 相似文献
12.
M. Sadeghi P. Sarabadani H. Karami 《Journal of Radioanalytical and Nuclear Chemistry》2010,283(2):297-303
Maghemite nano-particles were synthesized by a solid-state chemical reaction for its highly selective use as, cyclotron-produced,
109Cd (462.9 days) purification method of choice. 109Cd radiochemical separation starts with Ag activities precipitated with HCl 0.0015 M followed by, on a second step, 109Cd separation from Cu carrier and 65Zn (243.8 days) using Ca (NO3)2 0.01 M. Experimental parameters such, pH and sorbent concentration, on 109Cd extraction efficiency were investigated. Phase morphology, nanostructure and size of nano-particles were studied by X-ray
diffraction (XRD) and scanning electron microscopy (SEM). A 10–20 nm average grain size was derived from XRD line broadening
and SEM data. Heat treatment on Fe3+:Fe2+ ratios equal to 2:1, produced powders, resulting in tetragonal (maghemite) structure at 300 °C and rhombohedra (hematite)
at 600 °C. 109Cd chemical and radionuclidic purity were determined by ICP-AES and HPGe detector gamma-ray spectrometry. The overall recovery
and radionuclide purity were 80.0% from obtained 129.63 kBq/C MeV (70 kBq/μAh) initial activity and 91.4%, respectively. 相似文献
13.
M. L. Bonardi F. Groppi C. Birattari L. Gini C. Mainardi A. Ghioni E. Menapace K. Abbas U. Holzwarth M. F. Stroosnijder 《Journal of Radioanalytical and Nuclear Chemistry》2003,257(1):229-241
Copper-64 is a radionuclide suitable for labeling of a wide range of radiopharmaceuticals for PET imaging, as well as systemic or local radioimmunotherapy of tumors. Among the possible methods for cyclotron production of No Carrier Added (NCA) 64Cu (61Cu), we investigated the deuteron irradiation on natural Zn target, via (d,axn) and (d,2pxn) nuclear reactions. This paper reports the preliminary results about the experimental determination and theoretical calculation of thin-target excitation functions in the energy range up to 19 MeV for 61Cu, 64Cu, 66Ga, 67Ga, 65Zn and 69mZn. A fast selective radiochemical separation of NCA 64Cu from Zn target and Ga radionuclides, with quality control tests is described too. 相似文献
14.
M. Sadeghi H. Karami P. Sarabadani F. Bolourinovin 《Journal of Radioanalytical and Nuclear Chemistry》2009,281(3):619-623
The 109Cd radionuclide was produced in the cyclotron via natAg(p,n)109Cd reaction. The radiochemical separation of 109Cd from silver and non-isotopic impurities comprised of two stages. The optimum conditions of the 109Cd separation methods were: Ag precipitation with 0.015 M HCl and Cu and 65Zn by use of 0.015 M HCl on AG1-X8 strong anion-exchange resin. Chemical and radionuclidic purity of 109Cd were measured by ICP-AES and gamma-ray spectrometry respectively. Recovery yield and radionuclidic purity were obtained 99.7% and 99%, respectively. 相似文献
15.
Yousef Fazaeli Amir R. Jalilian Mostafa M. Amini Ali Rahiminejad-kisomi Saeed Rajabifar Fatemeh Bolourinovin Sedigheh Moradkhani 《Journal of Radioanalytical and Nuclear Chemistry》2011,288(1):17-24
[67Ga]labeled tetraphenyl porphyrin ([67Ga]-TPP) was prepared using freshly prepared [67Ga]GaCl3 and tetraphenyl porphyrin (TPPH2) for 30–60 min at 25 °C (radiochemical purity: >97 ± 1% ITLC, >98 ± 0.5% HPLC, specific activity: 13–14 GBq/mmol). Stability
of the complex was checked in final formulation and human serum for 24 h. The partition coefficient was calculated for the
compound (log P 1.89). The biodistribution of the labeled compound in vital organs of wild-type rats was studied using scarification studies
and SPECT imaging up to 24 h. A detailed comparative pharmacokinetic study performed for 67Ga cation and [67Ga]-TPP. The complex is mostly washed out from the circulation through kidneys and can be an interesting tumor imaging/targeting
agent due to low liver uptake and rapid excretion through the urinary tract. 相似文献
16.
H. M. Talaat A. A. El-Mohty M. T. El-Kolaly 《Journal of Radioanalytical and Nuclear Chemistry》2010,284(1):1-5
Improved radionuclide generator include a substantially insoluble salt of a radioactive parent which may be directly packed
in column for subsequent elution of the daughter radionuclide. An improved 188Re generator was prepared by reacting a radioactive tungsten (188W) as parent radionuclide incorporated with aluminum chloride to obtain an insoluble radioactive aluminum tungstate matrix.
The investigated matrix was characterized on the basis of the chemical composition, IR, thermal analysis and mechanical stabilities.
The factors affecting the elution performance were studied such as influence of pH, molar ratio and drying temperature. From
the obtained data, the molar ratio W:Al was 1.5:1 at pH = 4, the matrix dried at 105 °C for 2 h. Chromatographic and multichannel
analysis has been currently used to investigate the radiochemical and radionuclidic purity respectively on eluted 188Re. An elution yield more than 80%, with radiochemical purity <98% and radionuclidic purity <99% with a 188W break through >10−4% of the column. The Al+3 and W contents value were about 2 and 3 μg/mL eluate. The obtained data approved the stability of the prepared generator
and its suitability for medical application. 相似文献
17.
K. Aardaneh T. N. van der Walt C. Davids 《Journal of Radioanalytical and Nuclear Chemistry》2006,270(2):385-390
Summary Ion-exchange chromatography using the chelating resins Purolite S950 and Chelex 100 was investigated for the radiochemical
separation of 82Sr from a RbCl target. 0.25M NH4Cl solution was employed for the retention of Sr and elution of Rb, and 2M HCl for the elution of Sr. Although both resins
showed very similar results, the conditions for adsorption of Sr were different. The ammonium chloride solution was directly
used with Purolite S950 while it was necessary to adjust the pH between 9 and 10 with Chelex 100. Purolite S950 was, therefore,
selected for routine production of 82Sr. A procedure has been introduced for the preparation of a hydrous tin dioxide as supporting material for the 82Sr/82Rb generator column. All components of the generator column were made up of stainless steel. The column was 4 cm long, 9.5
mm O.D. and 7.1 mm I.D. Using isotonic saline (0.9% NaCl) for elution of 82Rb, elution curves with different flow rates ranging from 5 to 20 ml/min were obtained. Maximum available 82Rb was eluted in the first 20 ml. The column generator provided a sterile 82Rb in isotonic saline. The breakthrough of 82Sr over 4 weeks of elution using 7 liter of saline was on average 4.5 . 10-5% (based on the first 20 ml eluate). 相似文献
18.
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
19.
A. R. Jalilian L. Mirsadeghi Y. Yari-kamrani P. Rowshanfarzad M. Kamali-dehghan M. Sabet 《Journal of Radioanalytical and Nuclear Chemistry》2007,274(3):563-568
Copper-64 was produced as a by-product of 55Co via 64Ni(p,n)64Cu by 15 MeV proton bombardment of natNi resulting in a thick target yield of 5.31 MBq/μAh (143.5 μCi/μAh) and a radiochemical separation yield of 95% (radionuclide
purity >97% after 25 hours of bombardment). Rituximab was successively labeled with [64Cu]-CuCl2. N-succinimidyl-1,4,7,10-tetraazacyclododecane-1,4,7,10-tetraacetic acid (DOTA-NHS) was prepared at 25 °C using DOTA and
N-hydroxy succinimide (NHS) in CH2Cl2 followed by the addition of 1 ml of a Rituximab pharmaceutical solution. Radiolabeling was performed at 37 °C in 3 hours.
Radio thin-layer chromatography showed an overall radiochemical purity of 90–95% at optimized conditions (specific activity=30
GBq/mg, labeling efficacy; 82%) using various chromatography systems. The final isotonic 64Cu-DOTA-Rituximab complex was passed through a 0.22 μm filter and checked by gel electrophoresis for radiolysis control. Stability
of the final product was checked in the formulation and in presence of human serum at 37 °C. 相似文献
20.
Ethyl-substituted bis-triazinylpyridine (Et-BTP), a nitrogen containing soft-donor extractant, was used in investigations
pertaining to the separation of Am3+ and Eu3+ from dilute nitric acid feed solutions by extraction chromatography using XAD-4 as the inert support, chlorinated dicarbollide
as the modifier and 2-nitrophenyloctylether (NPOE) as the diluent. After carrying out a series of experiments, the optimum
composition of the extractant mixture for the resin was found out to be 0.1 M Et-BTP and 0.025 M CCD in NPOE. Separation factor
values were encouraging to carry out subsequent batch uptake studies at varying nitrate ion concentration which indicated
favourable separation behaviour up to NaNO3 concentration of 2 M. Column studies have been carried out and conditions for elution and separation of Am3+ from Eu3+ have been found out. Long term stability of the resin was also investigated. 相似文献