共查询到20条相似文献,搜索用时 15 毫秒
1.
T. Fujii H. Yamana M. Watanabe H. Moriyama 《Journal of Radioanalytical and Nuclear Chemistry》2001,247(2):435-437
Extraction behaviors of Pd(II) in the TRUEX and PUREX solvent extractions were studied by using octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide. The effect of scrubbing in the TRUEX solvent extraction was demonstrated by adding oxalic acid. The distribution ratios of palladium (D
Pd's) in the diluted region of [HNO3] were found to depend strongly on the fraction of cationic species, Pd(NO3)+, existed in the aqueous phase. The gradual decrease of DPd with the increase of acidity beyond [H+] 1 mol·dm-3 was controlled by the formation of the anionic species Pd(NO3)3
-. 相似文献
2.
L. Pietrelli A. Salluzzo F. Troiani 《Journal of Radioanalytical and Nuclear Chemistry》1990,141(1):107-115
The octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (CMPO), loaded as stationary phase on silica, has been used for the sorption of Eu and actinides from acidic aqueous solution. Different commerical solid support were investigated and, finally SiO2 was chosen. Experiments were performed to obtain basic data on actinide removal. Distribution coefficients, kinetics, sorption isotherms (three adsorption model correlations were tested) and the acidic concentration effect were studied. 相似文献
3.
C. S. Pawaskar P. K. Mohapatra V. K. Manchanda 《Journal of Radioanalytical and Nuclear Chemistry》1999,242(3):627-634
The extraction behavior of several metal ions viz., Am3+, Eu3+, UO2
2+, Th4+, Sr2+ and Cs+ was investigated from sulphate medium employing phosphotungstic acid (PTA) and polyethylene glycol (PEG). The influence of
various parameters such as pH, PTA concentration, PEG concentration and salt concentration was studied. The order of extraction
followed the trend: Am3+>Eu3+>>Th4+>UO2
2+>Sr2+>Cs+ which deviate significantly from the reported order with conventional solvents. The relatively poor extraction of UO2
2+, Sr2+ and Cs+ was ascribed to their lack of interaction with the phosphotungstate anion. The separation behaviour of Am3+ vis-a-vis Eu3+ was also investigated under different experimental conditions. 相似文献
4.
J. N. Mathur M. S. Murali P. R. Natarajan L. P. Badheka A. Banerji K. M. Michael S. C. Kapoor R. K. Dhumwad 《Journal of Radioanalytical and Nuclear Chemistry》1992,165(4):219-227
The tail-end purification of Am from Pu loading effluents in 7.5M HNO3 containing 160 mg l–1 Am and 1.2 mg l–1 Pu has been carried out. With 0.2M CMPO+1.2M TBP in dodecane as the extractant and stripping by 0.04M HNO3+0.05M NaNO2, the Pu level is brought down to 31.2 g l–1. When the acidity was reduced to 4.2M HNO3, one contact with 20% TLA/dodecane and subsequent extraction by a mixture of CMPO and TBP and stripping with 0.04M HNO3+0.05M NaNO2 gave Am samples without any detectable amounts of Pu. The recovery of Am was 90% by the first procedure and 98% by the second one. 相似文献
5.
A. V. Jadhav V. K. Goyal S. N. Pattanaik P. S. Shankaran S. K. Patil 《Journal of Radioanalytical and Nuclear Chemistry》1984,82(2):229-245
The extraction of Am(III), Pu(IV) and U(VI) as representatives of tri-, tetra- and hexavalent actinides by dibutyl-N,N-diethylcarbamoylmethylenephosphonate (DBDECMP) from nitric acid solution has ben studied with an objective of understanding the extraction mechanism. The dependence of the distribution ratios of the actinide ions was studied as a function of the concentration of H+, DBDECMP and NO
3
–
. The extraction data revealed that all the three actinide ions are extracted as their neutral nitrate complexes solvated by DBDECMP which behaves as neutral extractant only. The absorption spectra of DBDECMP and TBP extracts of these actinide ions were recorded. From the close similarity of these spectra it is inferred that DBDECMP acts as a monodentate extractant in the present system. 相似文献
6.
K. V. Lohitakshan P. D. Mithapara P. S. Nair S. A. Pai K. Raghuraman A. V. Jadhav H. C. Jain 《Journal of Radioanalytical and Nuclear Chemistry》1994,183(2):359-370
Extraction of trivalent (Pu3+, Am3+, actinides and Eu3+, a representative of lanthanides) and tetravalent (Np4+ and Pu4+) actinides has been studied with dihexyl N,N-di-ethylcarbamoylmethyl phosphonate (DHDECMP) in combination with TBP in benzene from 2M nitric acid. The stoichiometries of the species extracted were found to be M(NO3)3·(3–n) TBP·n DHDECMP (for trivalent ions) and M(NO3)4·(2–n) TBP·n DHDECMP (for tetravalent ions) by the slope ratio method. The extraction constants evaluated (from the distribution data) indicate that for tetravalent ions (with solvation number two) the extraction constant increases when TBP (Kh=0.17) molecules are successively replaced by more basic DHDECMP (Kh=0.34) molecules. However, for trivalent ions (with solvation number three) when TBP molecules are totally replaced by DHDECMP molecules stereochemical factors appear and instead of increase, a substantial decrease in extraction constants is observed for Eu3+ and Am3+, a lesser decrease being observed for Pu3+ (larger ion). 相似文献
7.
8.
A. Zhang Y. Wei M. Kumagai Y. Koma 《Journal of Radioanalytical and Nuclear Chemistry》2006,269(1):119-128
Summary The Minor Actinides Recovery from HLW by Extraction Chromatography (MAREC) process was used mainly for the separation of minor
actinides (MAs) and some specific fission products (FPs) from highly active liquid waste (HLW) by the composite CMPO/SiO2-P of the macroporous silica based polymeric octyl(phenyl)-N,N-diisobutylcarbamoylmethylphoshine oxide (CMPO) and others.
In this study a cascade of chromatographic separation was performed on a 3.0M HNO3 solution containing 5.0 . 10-3M of 13 elements, at 323 K. The cascade consisted of three columns the first and second ones were packed with CMPO/SiO2-P and the third with SiO2-P particles. The first column was employed to prepare various eluents containing saturated CMPO. The second column was used
for separation into groups. The CMPO of CMPO/SiO2-P was recovered from the effluent by the third column and a CMPO-free effluent containing minor actinides was obtained. The
elements contained in the simulated HLW of 3.0M HNO3 were separated into (1) a non-adsorption group (Sr, Cs, and Ru etc.), (2) a MA-hRE (heavy rare earth)-Mo-Zr group, and (3) a lRE (light rare earth) group by eluting with 3.0M HNO3, 0.05M DTPA (diethylenetriaminepentaacetic acid) (pH 2.0) and HNO3 (pH 3.5), respectively. The resultant MA-hRE-Mo-Zr mixture containing minor actinides was then separated into the groups (1) Pd-Ru, (2) MA-hRE, and (3) Mo-Zr by utilizing 3.0M HNO3, distilled water, and 0.05M DTPA (pH 2.0) as eluents. More than 92% of CMPO in the MA-hRE containing effluent was adsorbed by SiO2-P particles. The effectivity and technical feasibility of MAREC process were demonstrated. 相似文献
9.
G. A. Pribylova 《Journal of Radioanalytical and Nuclear Chemistry》2011,288(3):693-697
Influence of ionic liquids (ILs) addition (1?C50 wt%) on extraction efficiency of actinides by diphenyl(dibutyl)carbamoylmethylphosphine oxide (Ph2Bu2) from 3 M HNO3 has been studied. Am(III) distribution ratios in two-phase systems 0.1 M Ph2Bu2 in either DCE or CHCl3?C3 M HNO3 depending on the nature of additional ionic liquids: imidazolium-based ILs: [C4mim][PF6], [C4mim][BF4] and phosphonium-based ILs: PPF6, PBF4 and PCl were determined. The highest value of Am(III) extraction ratio change (1040) was found on addition of PPF6 to Ph2Bu2 in CHCl3. Extraction of Pu(IV) and U(VI) by 0.001 M Ph2Bu2 in the presence of [C4mim][PF6] in DCE, CHCl3 or meta-nitrobenzotrifluoride (NBTF) have been investigated. The greatest enhancement of extraction efficiency was observed using CHCl3, the least polar studied solvent. Using a mixture of conventional solvent and ionic liquid as a solvent for extractant enables one to increase distribution ratios and reduce viscosity of organic phase as compared with ionic liquid viscosity. The marked increase of Am(III), Pu(IV) and U(VI) extraction extent by Ph2Bu2 on addition of ionic liquids to the extent of 10 wt% permit one essentially to diminish amounts considerably more expensive carbamoylmethylphosphine oxide(the general name is CMPO) used in TRUEX process. 相似文献
10.
Stockmann TJ Lu Y Zhang J Girault HH Ding Z 《Chemistry (Weinheim an der Bergstrasse, Germany)》2011,17(47):13206-13216
The complexation reactions between strontium (Sr(2+)) and octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (CMPO) were studied at the aqueous|1,2-dichloroethane (w|DCE) and aqueous|room-temperature ionic liquid (w|RTIL) microinterfaces, in order to understand its extraction in reprocessing spent nuclear fuels, remediation of environmental contamination, and potential radiological isotope feed stock for (90)Y from its isotope (90)Sr in fission byproducts. The stoichiometry (or metal to ligand ratios) and overall complexation constant (β) for these reactions at these two interfaces are described herein. Two stoichiometries at the w|DCE interface were discovered, that is, [Sr(CMPO)(2)](2+) and [Sr(CMPO)(3)](2+) with β values of 4.5×10(19) and 5.5×10(25), respectively. Only one stoichiometry was observed at the w|RTIL interface: [Sr(CMPO)(3)](2+) with β equal to 1.5×10(34). The larger complexation constant for [Sr(CMPO)(3)](2+) at the w|RTIL interface than those found at the w|DCE interface supported the previous observation of a greater distribution ratio in the aqueous-RTIL metal extraction than that in the aqueous-alkane processing. The kinetics of the reactions at the w|RTIL interface was slow. The stoichiometries at the w|DCE interface were confirmed using biphasic electrospray ionization mass spectrometry (BESI-MS) as well as direct injection of Sr(2+) and CMPO mixture by means of a "shaking flask" experiment to conventional ESI-MS. 相似文献
11.
Vanadium(V) extraction with octyl alcohol isomers from acid solutions was studied. Two areas are determined, wherein the vanadium(V) extraction in relation to acidity of the aqueous phase is maximal. The opposite effects of temperature on the extraction are found. The mechanism of the vanadium(V) extraction with high molecular weight alcohols from weakly acid solutions was suggested. 相似文献
12.
P. Selucký J. Rais M. Kyrš L. Kadlecová 《Journal of Radioanalytical and Nuclear Chemistry》1991,148(2):227-233
The dependence of the distribution of Cs, Sr, Ba, Eu, Ce between nitric acid solutions and 0.06M hexabromo derivative of cobalt dicarbollide (H+BBr
6
–
) in dichloroethane has been investigated upon the concentration of the acid, the extractant and the synergistic additive Slovafol 909. The back-extraction due to the presence of propanol, hydrazine, nitric acid and NH4NO3 has been studied. The results were similar to those observed in analogous systems using nitrobenzene as the solvent. 相似文献
13.
G. X. Sun Y. S. Wang S. X. Sun B. R. Bao 《Journal of Radioanalytical and Nuclear Chemistry》1997,221(1-2):219-220
The partition of uranium(VI) between nitric acid solutions and solutions of N,N-dibutyldodecanamide (DBDA) in kerosene has been investigated at varying concentrations of nitric acid, extractant, salting-out agent LiNO3 and at different temperatures. The mechanism of extraction is discussed in the light of the results obtained. 相似文献
14.
《Journal of Inorganic and Nuclear Chemistry》1978,40(6):1147-1151
Butyl lauryl phosphoric acid (HBLP) was chosen as a model compound of secondary degradation products of Purex process solvent. The extent of zirconium complexation by this compound is similar to that of dibutyl phosphoric acid or bis(2 ethyl hexyl) phosphoric acid. The mechanism of zirconium extraction by HBLP was studied. The nature of the extracted species could not be unambiguously established. Tributyl phosphate has an antagonistic effect on the zirconium extraction by HBLP. Removal of HBLP from the solvent cannot be accomplished by alkaline washes representative of solvent clean-up procedures used in the Purex process. This could lead to a long term build-up of this type of compound under Purex processing conditions. The threshold HBLP concentration for an enhancement of zirconium extraction is 2 × 10−4 M. 相似文献
15.
V. R. Bhandiwad Rajendra Swarup S. K. Patil 《Journal of Radioanalytical and Nuclear Chemistry》1979,52(1):5-14
The extraction of Np(IV), Pu(IV) and U(VI) from aqueous hydrochloric acid into quaternary amines has been studied. The dependence
of the distribution coefficient on amine concentration suggests that the actinide ions extracted are NpCl
6
2−
PuCl
6
2−
and UO2Cl
4
2−
. This is further supported by the absorption spectra of the amine extracts of these actinide ions. Based on the extraction
data obtained, a simple method for the separation of typical metal ions such as Cs, lanthanides and Zr from U(VI) and Pu(IV)
is suggested. 相似文献
16.
J. Příhoda 《Journal of Radioanalytical and Nuclear Chemistry》1979,51(2):233-243
Liquid-liquid extraction of divalent palladium by solutions of Diesel oil (D.O.) and gas oil II (G.O.II) in benzene and lacquer
petroleum from nitrate media has been studied. Palladium in concentrations of ∼10−3M is very effectively extracted by dilute solutions of extraction reagents and the distribution of palladium is almost independent
of the acidity and nitrate concentration of the aqueous phase. Of other common salts, chlorides, thioeyanates and nitrites
affect the palladium distribution. In many cases high concentrations of salts completely suppress the extraction of palladium.
The rate of palladium extraction by dilute solutions of extractants is relatively small. Some substances such as dimethyl
sulfoxide (DMSO) were found to accelerate the extraction. Palladium extraction from nitric acid media also has been studied
from the points of view of chemical and radiation stability. Diesel oil was found to be a more stable extraction reagent in
acid media than gas oil II. 相似文献
17.
J. N. Mathur M. S. Murali P. R. Natarajan 《Journal of Radioanalytical and Nuclear Chemistry》1992,162(1):171-178
Batchwise uptake of Am(III), Pm(III), Eu(III), U(VI) and Pu(IV) by dihexyl-N,N-diethylcarbamoylmethylphosphonate (CMP) adsorbed on chromosorb (CAC) at nitric acid concentrations between 0.01 to 6.0M has been studied. The difference between the uptake behavior of Pu(IV) as compared to other actinides and lanthanides is discussed. The Am(III) and U(VI) species taken up on CAC were found to be Am(NO3)3·3CMP and UO2(NO3)2·2CMP, respectively. The equilibrium constants for the formation of these species have been evaluated and compared with those of similar species formed in liquid-liquid extraction. Batchwise loading of Pm(III) on CAC from 3.0M HNO3 has also been studied. 相似文献
18.
Alpha emitting actinides such as plutonium, americium or curium were measured by alpha-spectrometry after radiochemical separation. The short range of alpha-particles within matter requires, after a pre-concentration process, a succession of isolation and purification steps based on the valence states modification of the researched elements. For counting, actinides were electrodeposited in view to obtain the mass-less source necessary to avoid self-absorption of the emitted radiations. Activity concentrations of gamma-emitting fission products were calculated after measurement with high purity germanium detectors (HPGe). These different methods were used to analyse soils sampled in the Republic of Belarus, not far from the Chernobyl nuclear plant. 相似文献
19.
A method for the separation of zirconium from fission products based on the system 100–200 mesh silica gel—2.0 M nitric acid is described. Decontamination factors are over 500 for 95Nb, 106Ru, 124Sb, 137Cs, molybdate and uranium(VI), and the yield of zirconium is 98 %. 相似文献
20.
Extraction behavior of Th(IV) and U(VI) has been investigated with bis(2-ethylhexyl) phosphinic acid (PIA-8) and bis(2-ethylhexyl) phosphoric acid (HDEHP) from nitric acid media in toluene. The optimum conditions for extraction of these metals have been established by studying various parameters like acid concentration, pH, reagent concentration, diluents and shaking time. The extraction of Th(IV) was found to be quantitative with 0.3-2.5M HNO3 by 2.5.10-2M HDEHP and in the pH range 0.1-2.5 with 2.3.10-2M PIA-8 in toluene. U(VI) was completely extracted in the acidic range of 0.1-2.0M HNO3 with 2.2.10-2M HDEHP and in the pH range of 1.0-3.0 with 2.0.10-2M PIA-8 in toluene. The probable extracted species have been ascertained by log D-log c plot as UO2 R2
.2HR with both the reagents and Th (NO3)2R2
.2HR with PIA-8 and Th (NO3)3R.3HR with HDEHP, respectively. Temperature dependence of the extraction equilibrium is examined by the temperature variation method. Separation of U(VI) and Th(IV) was also carried out from commonly associated metals. 相似文献