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Wyświetlanie 1-15 z 16
Tytuł:
Actinide ion exchange technology in the back end of the nuclear fuel cycle
Autorzy:
Navratil, J.
Wei, Y.
Powiązania:
https://bibliotekanauki.pl/articles/147559.pdf
Data publikacji:
2001
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
actinide separation and purification
adsorption and elution
ion-exchange resin
separation
Opis:
Ion exchange is used extensively in nuclear power technology, especially for uranium ore processing, removal of contaminants from power reactor waters and in the back end of the nuclear fuel cycle. In nuclear fuel reprocessing plants, ion exchange is used for the purification of actinide elements for further use, for the solidification of low- and medium-active waste solutions, and for the partitioning of high-level wastes. This paper reviews selected technological uses of ion exchange in these operations for recovery, separation and purification of selected actinides (Pu, U, Np, etc.). Recent research and development on ion exchange technologies for actinides are also summarized.
Źródło:
Nukleonika; 2001, 46, 2; 75-80
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Production and quality control of 66Ga radionuclide
Autorzy:
Sabet, M.
Rowshanfarzad, P.
Jalilian, A.
Ensaf, M.
Rajamand, A.
Powiązania:
https://bibliotekanauki.pl/articles/146278.pdf
Data publikacji:
2006
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
gallium-66
cyclotron
radiochemical separation
target recovery
Opis:
The purpose of this study was to develop the required targetry and radiochemical methods for production of 66Ga, according to its increasing applications in various fields of science. The 66Zn(p,n)66Ga reaction was selected as the best choice for the production of 66Ga. The targets were bombarded with 15 MeV protons from cyclotron (IBA-Cyclone 30) at the Nuclear Research Center for Agriculture and Medicine (NRCAM) with a current of 180 mA for 67 min. ALICE and SRIM (Stopping and Range of Ions in Matter) nuclear codes were used to predict the optimum energy and target thickness. Targets were prepared by electroplating 95.73% enriched 66Zn on a copper backing. Chemical processing was performed by a no-carrier-added method consisting of ion exchange chromatography and liquid-liquid extraction. Anion exchange chromatography was also used for the recovery of target material. Quality control of the product was carried out in two steps of chemical and radionuclide purity control. The activity of 66Ga was 82.12 GBq at EOB and the production yield was 410.6 MBq/mAh. The radiochemical separation yield was 93% and the yield of chemical recovery of the target material was 97%. Quality control tests showed a radionuclide purity higher than 97% and the amounts of chemical impurities were in accordance with the United States Pharmacopoeiae levels.
Źródło:
Nukleonika; 2006, 51, 3; 147-154
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Isotope effects of gallium and indium in cation exchange chromatography
Autorzy:
Dembiński, W.
Herdzik, I.
Skwara, W.
Bulska, E.
Wysocka, A.
Powiązania:
https://bibliotekanauki.pl/articles/146163.pdf
Data publikacji:
2006
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
isotope separation
chemical isotope effect
ion-exchange chromatography
Opis:
The isotope effects of gallium (69/71Ga) and indium (113/115In) have been determined in the system: strong cation exchanger (Dowex 50-X8)/HCl. The sings of gallium and indium effects were opposite, i.e., the heavier isotope of gallium was fractionated into the resin phase, while the heavy isotope of indium was fractionated into the liquid phase. The values of unit separation gains were found to be +3.0 ´ 10-5 for gallium and –2.0 ´ 10-4 for indium. A possible explanation of the effects is proposed.
Źródło:
Nukleonika; 2006, 51, 4; 217-220
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Technical solutions for the control and command system of a Plasma Focus device
Autorzy:
Martin, D. I.
Zoita, V. I.
Cotruta, D. A.
Jianu, A. V.
Ighigeanu, D. I.
Bestea, V. I.
Powiązania:
https://bibliotekanauki.pl/articles/147621.pdf
Data publikacji:
2001
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
control system
electromagnetic transients
galvanic separation
plasma focus
Opis:
The paper presents the technical problems related to the electrical control and command system (ECC system) for the plasma focus installation IPF-4/5A having the following main parameters: 1 MA plasma current and 40 kJ energy stored at 20 kV charging voltage. The ECC system applies 23 interlocked logical commands, acquires and processes 28 logical states, acquires, processes and displays continuously the main slow-varying signals coming from IPF-4/5A subassemblies. All the plasma focus installation operational sequences are governed by strict hard and soft interlocking using in parallel two control and command systems: one based on PC-control methods and another based on classical control techniques.
Źródło:
Nukleonika; 2001, 46, suppl. 1; 89-91
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Production and quality control of 65Zn radionuclide
Autorzy:
Rowshanfarzad, P.
Jalilian, A.
Sabet, M.
Powiązania:
https://bibliotekanauki.pl/articles/148866.pdf
Data publikacji:
2005
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
zinc-65
production
cyclotron
radiochemical separation
quality control
Opis:
Zinc-65 was produced in the Nuclear Research Center for Agriculture and Medicine (NRCAM) by the bombardment of natural copper targets with 30 MeV protons via the 65Cu(p,n)65Zn nuclear reaction. Natural copper was used instead of enriched 65Cu because of the quick decay of undesired radioisotopes. It was also more desirable for cost effectiveness. Cross-section calculations were performed by ALICE nuclear code and the results were compared with the experimental data given in the literature, which showed good agreement. A 160 mi m copper layer target was bombarded with a 150 miA current of 30 MeV protons for 20 min, which resulted in 170 MBq activity of 65Zn product. The yield was 3.4 MBq/miAh. The concentration of the product was 6.8 MBq/ml. Radiochemical separation was carried out by anion exchange chromatography with the yield of about 98%. Quality control of the final product showed a radionuclide purity of more than 98% and no traces of possible impurities (copper) were detected by a colorimetric method with a 1 ppm detection limit using dithizone as the reagent. The materials used for targetry and chemical separation were quite cost-effective.
Źródło:
Nukleonika; 2005, 50, 3; 97-103
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
A study of cerium extraction by TBP and TODGA using a rotating diffusion cell
Autorzy:
Bromley, M. A.
Boxall, C.
Powiązania:
https://bibliotekanauki.pl/articles/148471.pdf
Data publikacji:
2015
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
SACSESS
TBP
TODGA
rotating diffusion cell (RDC)
separation
extraction
Opis:
For the study of the coupled interfacial-mass transfer kinetics of, inter alia, TBP, TODGA, CyMe4-BTBP and CyMe4-BTPhen based solvent extraction processes, a new rotating diffusion cell (RDC) apparatus has been established at Lancaster University. RDC studies of Ce(IV)/TBP and Ce(III)/TODGA extraction systems have been undertaken in order to improve the understanding of the chemical and kinetic processes involved. In each case, an interesting dependency on local hydrodynamics at the solution phase boundary with results suggesting that the organic extractant molecules migrate into the aqueous phase in order to capture Ce.
Źródło:
Nukleonika; 2015, 60, No. 4, part 2; 859-864
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Thermochromatographic separation of 206,208Po from a bismuth target bombarded with protons
Autorzy:
Wąs, B.
Misiak, R.
Bartyzel, M.
Petelenz, B.
Powiązania:
https://bibliotekanauki.pl/articles/148537.pdf
Data publikacji:
2006
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
thermochromatographic separation
radionuclides 206Po and 208Po
environment
Opis:
The artificially produced isotopes of polonium are valuable tracers for radiochemical procedures for the determination of natural 210Po. In this work, the isotopes of polonium (206Po to 208Po) were produced by activation of metallic bismuth targets with 40 MeV protons. The thick target yield of 206Po was 16 MBq/ěAh. Polonium was separated from bismuth by a thermochromatographic method under reduced pressure in static conditions. The bismuth target can be considered as the multiple-use material.
Źródło:
Nukleonika; 2006, 51,suppl.2; 3-5
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Uranium and neodymium partitioning in alkali chloride melts using low-melting gallium-based alloys
Autorzy:
Melchakov, S. Y.
Maltsev, D. S.
Volkovich, V. A.
Yamshchikov, L. F.
Lisienko, D. G.
Osipenko, A. G.
Rusakov, M. A.
Powiązania:
https://bibliotekanauki.pl/articles/146407.pdf
Data publikacji:
2015
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
neodymium
uranium
gallium
separation factor
reductive extraction
pyrochemical reprocessing
Opis:
Partitioning of uranium and neodymium was studied in a ‘molten chloride salt – liquid Ga-X (X = In or Sn) alloy’ system. Chloride melts were based on the low-melting ternary LiCl-KCl-CsCl eutectic. Nd/U separation factors were calculated from the thermodynamic data as well as determined experimentally. Separation of uranium and neodymium was studied using reductive extraction with neodymium acting as a reducing agent. Efficient partitioning of lanthanides (Nd) and actinides (U), simulating fission products and fissile materials in irradiated nuclear fuels, was achieved in a single stage process. The experimentally observed Nd/U separation factor valued up to 106, depending on the conditions.
Źródło:
Nukleonika; 2015, 60, No. 4, part 2; 915-920
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
TS-BTPhen as a promising hydrophilic complexing agent for selective Am(III) separation by solvent extraction
Autorzy:
Kaufholz, P.
Sadowski, F.
Wilden, A.
Modolo, G.
Lewis, F. W.
Smith, A. W.
Harwood, L. M.
Powiązania:
https://bibliotekanauki.pl/articles/147226.pdf
Data publikacji:
2015
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
Am-Cm separation
TODGA
TS-BTPhen
liquid-liquid extraction
Opis:
The novel hydrophilic back-extraction agent TS-BTPhen (3,3',3'',3'''-[3-(1,10-phenanthroline-2,9- -diyl)-1,2,4-triazine-5,5,6,6-tetrayl]tetrabenzenesulfonic acid) was tested for its selectivity towards Am(III) over Cm(III) and Eu(III) with a TODGA (N,N,N',N'-tetraoctyldiglycolamide) based solvent. Batch experiments were carried out using TS-BTPhen dissolved in aqueous nitric acid solution with tracers of 152Eu, 241Am and 244Cm. A signifi cant increase of the separation factor for Cm over Am from SFCm/Am = 1.6 up to SFCm/Am = 3.3 was observed compared to the use of a TODGA-nitric acid system alone. Furthermore, stripping was possible at high nitric acid concentrations (0.6–0.7 mol/L) resulting in a low sensitivity to acidity changes. The infl uence of the TS-BTPhen concentration was analyzed. A slope of –2 was expected taking into account literature stoichiometries of the lipophilic analogue CyMe4BTPhen. However, a slope of –1 was found. Batch stripping kinetics showed fast kinetics for the trivalent actinides. As an alternative organic ligand the methylated TODGA derivate Me-TODGA (2-methyl-N,N,N',N'-tetraoctyldiglycolamide) was tested in combination with the hydrophilic TS-BTPhen. The Am(III) separation was achieved at even higher nitric acid concentrations compared to TODGA.
Źródło:
Nukleonika; 2015, 60, No. 4, part 2; 815-820
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Ion exchange investigation for recovery of uranium from acidic pregnant leach solutions
Autorzy:
Danko, B.
Dybczyński, R. S.
Samczyński, Z.
Gajda, D.
Herdzik-Koniecko, I.
Zakrzewska-Kołtuniewicz, G.
Chajduk, E.
Kulisa, K.
Powiązania:
https://bibliotekanauki.pl/articles/147778.pdf
Data publikacji:
2017
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
uranium recovery
acidic pregnant leach solution
ion exchange separation
Opis:
The article describes studies on the separation of uranium from acid pregnant leach solutions obtained from Polish uranium ores: dictyonema shales and sandstone rocks. Ion exchange chromatography was applied for uranium sorption, using commercially available, strongly basic anion exchanger, Dowex 1. In model experiments, the influence of degree of crosslinking of Dowex 1 on the efficiency of uranium extraction was investigated. The effect of H2SO4 concentration on the breakthrough curve of uranyl ions for the Dowex 1 resins, of different crosslinking: X4, X8 and X10, was examined. Unexpectedly high increase of exchange capacity of uranium was observed in case of Dowex 1X10. This gives potential opportunity of improving the effectiveness of uranium recovery process. Applying column packed with Dowex 1X10, ‘yellow cake’ with ca. 92% yield and high purity of recovered uranium was obtained. A block diagram of the procedure for uranium and lanthanides extraction from acidic leach liquor has been proposed.
Źródło:
Nukleonika; 2017, 62, 3; 213-221
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Structure and separation quality of various N- and O-donor ligands from quantum-chemical calculations
Autorzy:
Trumm, M.
Schimmelpfennig, B.
Geist, A.
Powiązania:
https://bibliotekanauki.pl/articles/148110.pdf
Data publikacji:
2015
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
actinide chemistry
extracting ligands
lanthanide chemistry
quantum chemistry
separation factor
Opis:
Although BTP (2,6-di(1,2,4-triazin-3-yl)pyridine) has been proven to be a highly effective N-donor ligand for the selective An(III)/Ln(III) separation, the origin of its selectivity is still under discussion. We present in this paper quantum-chemical calculations at the density functional theory (DFT) and MP2 level which highlight the role of the aquo ions in the separation process. Furthermore these data will be the reference for future force-field development to investigate the differences in An(III) complexation reactions compared to their Ln(III) counterparts.
Źródło:
Nukleonika; 2015, 60, No. 4, part 2; 847-851
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Cyclotron production of technetium radionuclides using a natural metallic molybdenum thick target and consequent preparation of [Tc]-BRIDA as a radio-labelled kit sample
Autorzy:
Targholizadeh, H.
Raisali, G.
Jalilian, A. R.
Rostampour, N.
Ensaf, M.
Dehghan, M. K.
Powiązania:
https://bibliotekanauki.pl/articles/148477.pdf
Data publikacji:
2010
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
technetium
molybdenum target
thermal spray method
technetium radiochemical separation
radio--labelling
Opis:
Numerous studies have focused on the use of accelerators for production of 99mTc, but all of these investigations have been performed at low-level currents. In this research, for the first time, we have constructed a high power level natural Mo target for production of 99mTc radioisotope using cyclotrons. A high purity natural molybdenum target (130 mg/cm2), suitable for proton beam power level of several kilowatts, has been constructed using a thermal spray coating method. The target was irradiated in a Cyclone30 accelerator using 160 mi A of 25 MeV proton beam energy for 1000 mi A-h. The activity of produced 99mTc was measured as 2.75 Ci. The technetium radionuclides produced were extracted using an MEK organic phase, followed by preparation of Tc-BRIDA as a radio-labelled kit sample. Animal biodistribution studies have been performed in rats. After administration of the radio-labelled Tc-BRIDA in rats, we observed most of the radioactivity accumulated in intestine as expected for IDA derivatives. The results of measurements show a successful production of Tc radionuclides (including 99mTc) in the bombarded target and subsequent labelling of the kit with Tc. It is anticipated that the developed coating method for the production of high power Mo targets using enriched 100Mo and a proton beam of about 1 mA is capable of producing about 100 Ci of 99mTc per irradiated target. The developed high power Mo target, if constructed using enriched 100Mo, could be a practical method for a large-scale production of 99mTc for local applications near cyclotron facilities.
Źródło:
Nukleonika; 2010, 55, 1; 113-118
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Working parameters of the electron - beam-generated ion source for ISOL facilities
Autorzy:
Yushkevich, Y. V.
Turek, M.
Mączka, D.
Pyszniak, K.
Słowiński, B.
Vaganov, Y. A.
Zubrzycki, J.
Powiązania:
https://bibliotekanauki.pl/articles/146648.pdf
Data publikacji:
2012
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
on-line isotope separation
short-lived nuclides
nuclear spectroscopy
ion sources
Opis:
An electron-beam generated plasma (EBGP) ion source for nuclear spectroscopy purposes at YASNAPP (YAdernaya Spektroskopya NA Putchkah Protonov - nuclear spectroscopy using proton beams) isotope separation on-line facility is presented. Working conditions both in on- and off-line mode are presented and discussed. Formation of a potential trap inside a discharge chamber is an advantage of the presented construction, enabling relatively high ionization efficiencies (2-5%) even for hard-to-ionize elements like Be, Ti, V, Zr, Nb, Mo, Tc, Ru, Rd, Hf, Ta, W, Re, Os, Ir, Pt. The paper presents estimation of critical values of working parameters that enable formation of the ion trap leading in consequence to high efficiency of ionization. The optimal temperature of the discharge chamber and cathode walls is found to be in the range 2600-2800 K. Calculations of the output rates of ions produced in the on-line mode are also presented as well as the constraints on the half-life time of obtained nuclides imposed by construction details like the target material and its thickness.
Źródło:
Nukleonika; 2012, 57, 3; 351-356
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
SACSESS : the EURATOM FP7 project on actinide separation from spent nuclear fuels
Autorzy:
Bourg, S.
Geist, A.
Narbutt, J.
Powiązania:
https://bibliotekanauki.pl/articles/971486.pdf
Data publikacji:
2015
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
actinide separation
minor actinides
nuclear fuel reprocessing
partitioning
solvent extraction
pyrochemical separations
Opis:
Recycling of actinides by their separation from spent nuclear fuel, followed by transmutation in fast neutron reactors of Generation IV, is considered the most promising strategy for nuclear waste management. Closing the fuel cycle and burning long-lived actinides allows optimizing the use of natural resources and minimizing the long-term hazard of high-level nuclear waste. Moreover, improving the safety and sustainability of nuclear power worldwide. This paper presents the activities striving to meet these challenges, carried out under the Euratom FP7 collaborative project SACSESS (Safety of Actinide Separation Processes). Emphasis is put on the safety issues of fuel reprocessing and waste storage. Two types of actinide separation processes, hydrometallurgical and pyrometallurgical, are considered, as well as related aspects of material studies, process modeling and the radiolytic stability of solvent extraction systems. Education and training of young researchers in nuclear chemistry is of particular importance for further development of this field.
Źródło:
Nukleonika; 2015, 60, No. 4, part 2; 809-814
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Numerical study on extraction of tritium generated in HMR by way of system composed of EXEL-process and thermal diffusion column cascade
Autorzy:
Shimizu, M.
Takeshita, K.
Powiązania:
https://bibliotekanauki.pl/articles/146995.pdf
Data publikacji:
2002
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
chemical exchange reaction
heavy water
isotope separation
thermal diffusion
trickel-bed reactor
tritium
Opis:
A new tritium extraction system composed of a trickle-bed hydrogen/water isotopic exchange column using a hydrophobic Pt-catalyst combined with an SPE-water electrolyser (EXEL-process) and a thermal diffusion column cascade was proposed for the removal of tritium from heavy water irradiated in HMR ((Heavy Water Moderated Power Reactor), volume of heavy water = 140 m3 and mean neutron flux = 5×1013 n/cm2s). Numerical study on the extraction of tritium from the heavy water was carried out and the dimensions of proposed system were determined under the conditions that the concentration of tritium in the heavy water was kept less than 2.5 Ci/lHW. The calculation results indicated that the proposed system was designed practically.
Źródło:
Nukleonika; 2002, 47,suppl.1; 89-93
0029-5922
1508-5791
Pojawia się w:
Nukleonika
Dostawca treści:
Biblioteka Nauki
Artykuł
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