Determination of Uranium and Plutonium in High Active Solutions by Extractive Spectrophotometry

Plutonium and uranium was extracted from nitric acid into trioctyl phosphine oxide in xylene. The TOPO layer was analysed by spectrophotometry. Thoron was used as the chromogenic agent for plutonium. Pyridyl azoresorcinol was used as chromogenic agent for uranium. The molar absorption coefficient for uranium and plutonium was found to be 19000 and 19264 liter/mole-cm, respectively. The correlation coefficient for plutonium and uranium was found to be 0.9994. The relative standard deviation for the determination of plutonium and uranium was found to be 0.96% and 1.4%, respectively.     

Ammonium uranyl carbonate (AUC) based process of simultaneous partitioning and reconversion for uranium and plutonium in fast breeder reactors (FBRs) fuel reprocessing

Ammonium uranyl carbonate (AUC) based process of simultaneous partitioning and reconversion for uranium and plutonium is developed for the recovery of uranium and plutonium present in spent fuel of fast breeder reactors (FBRs). Effect of pH on the solubility of carbonates of uranium and plutonium in ammonium carbonate medium is studied. Effect of mole ratios of uranium and plutonium as a function of uranium and plutonium concentration at pH 8.0–8.5 for effective separation of uranium and plutonium to each other is studied. Feasibility of reconversion of plutonium in carbonate medium is also studied. The studies indicate that uranium is selectively precipitated as AUC at pH 8.0–8.5 by adding ammonium carbonate solution leaving plutonium in the filtrate. Plutonium in the filtrate after acidified with concentrated nitric acid could also be precipitated as carbonate at pH 6.5–7.0 by adding ammonium carbonate solution. A flow sheet is proposed and evaluated for partitioning and reconversion of uranium and plutonium simultaneously in the FBR fuel reprocessing.     

Controlled potential coulometric determination of plutonium and uranium using a mercury pool electrode

Summary A simultaneous determination of plutonium and uranium in sulphuric acid solution by controlled potential coulometry is described. After a pre-electrolysis of 0.5 M sulphuric acid on a mercury pool electrode at +0.1 V vs. the saturated silver chloride electrode the sample is added to the electrolysis cell and plutonium and uranium are subsequently reduced at +0.1 V and –0.35 V respectively. High-fired plutonium-uranium oxides are dissolved by heating with sulphuric acid, nitric acid and ammonium sulphate. Results obtained are not biased and the precision is satisfactory. A mixed oxide pellet can be analysed in 2.5 hours. A detailed procedure is given.

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Coulometrische Bestimmung von Plutonium und Uran bei kontrolliertem Potential mit einer QuecksilberelektrodeAnwendung auf die Analyse von hochgeglühten Uran-Plutonium-Mischoxiden

Zusammenfassung Eine gleichzeitige Bestimmung von Plutonium und Uran in schwefelsaurer Lösung durch Coulometrie bei kontrolliertem Potential wird beschrieben. Nach einer Vorelektrolyse von 0,5 M Schwefelsäure an einer Quecksilberelektrode bei + 0,1 V, gemessen gegen die Silberchloridelektrode, wird die Probelösung in die Elektrolysezelle gebracht und Plutonium und Uran werden nacheinander bei +0,1 V bzw. –0,35 V reduziert. Hochgeglühte Plutonium-Uranoxide werden durch Erhitzen mit Schwefelsäure, Salpetersäure und Ammoniumsulfat gelöst. Die erhaltenen Ergebnisse sind richtig und die Genauigkeit ist befriedigend. Ein Mischoxidpellet kann in 2,5 h analysiert werden. Eine detaillierte Arbeitsvorschrift wird gegeben.

     

A spectrophotometric method for the determination of plutonium in fuel solutions

A spectrophotometric method is described in which microgram amounts of plutonium can be determined in the presence of uranium, thorium, fission products and cladding materials. Plutonium is extracted with TTA in xylene and reextracted into a solution of Arsenazo III. Zirconium is masked by a Fe(III)-EDTA mixture, fluoride ions by Al(III). 2 to 40 μg of plutonium are required for one analysis. The standard deviation is 1.3% at 15 μg plutonium.     

Chemical separation of plutonium

Plutonium in nanogram quantities was isolated from uranium targets irradiated with charged particles. High decontamination was achieved using a method that combines anion exchange with extraction chromatography in tributyl phosphate/hydrochlorid acid solution system.     

An improved method for the potentiometric determination of plutonium using cerium/IV/ as an oxidant

An improved method for the determination of plutonium in an aliquot using cerium/IV/ as an oxidant is reported. Plutonium is oxidized quantitatively to plutonium/VI/ in nitric acid medium by cerium/IV/, the excess of which is chemically destroyed in a single step by hydrochloric acid. Plutonium/VI/ is then reduced to plutonium/IV/ with a known amount of Fe/II/, the excess of which is back titrated potentiometrically with standard dichromate. Results of analysis of 3–5 mg amounts of plutonium in aliquots containing standard plutonium nitrate solution are reliable within 0.2%. Effect of the presence of some relevant foreign ions has been studied. The application of the method for the analysis of mixtures containing various amounts of uranium and plutonium has been examined.     

Is plutonium really a threat to man and his environment?

Plutonium is a vital source of energy. The importance of plutonium as a source of energy can easily be understood by a simple fact that the amount of energy produced from one gram of plutonium is equal to the energy produced from 100 g of uranium and/or one ton of oil. Plutonium poses little or no problem as a high level waste. This can be predicted from our earlier studies on Th in man which has indicated that the general population of the United States exposed to insoluble Th throughout the life times accumulates the amount of Th contained in 1–6 g of soil. Furthermore, the vitrification process can prevent the translocation of Pu into the environment from the waste storage site quite effectively. Plutonium is a great asset to the human race only if they are civilized and use this great element for their prosperity as a source of energy. However, if the people and/or their leaders become barbaric, inhumane, crazy and misguided, then Pu could be the greatest threat to the survival of human race. Therefore, man himself could become the greatest threat to the human race.     

Organic solvent extraction of uranium from alkaline nuclear waste

There are proliferation issues with the Plutonium Uranium Redox Extraction process due to the possibility of recovering plutonium. The objective of this research was to evaluate different organic extraction ligands that can remove uranium from the nuclear waste and to determine the most effective organic solvent for extracting uranium only, from alkaline media. The results indicate that Alamine 336 in xylene has zero (0%) extraction capability for surrogate fission products at an optimum extraction time of 15 min. Aliquat 336 in xylene has an extraction percentage of 72% for uranium in 60 min. However, Aliquat 336 in toluene extracted 82% of the uranium from the feed solution after 30 min, decreasing to 76% after 60 min.

     

Anion-exchange separation of plutonium in hydrochloric-hydrobromic acid media

Plutonium can be rapidly and selectively separated from the elements that interfere in its radiochemical determination, by the use of hydrobromic acid in a hydrohalic acid anion-exchange separation procedure. Plutonium(IV) and (VI) are adsorbed onto the resin column from 9M hydrochloric acid, interfering elements such as americium and thorium are washed from the column with 9M hydrochloric acid, and the plutonium is reduced to plutoniurn(III) and washed from the column with 11M hydrobromic acid. Interfering elements such as uranium and neptunium, which are adsorbed onto the column from 9M hydrochloric acid, are retained there during the hydrochloric and hydrobromic acid washes. This system would also appear to provide the means for effectively separating plutonium from those elements that commonly interfere in such chemical methods of analysis as redox titration.     

Plutonium metal standards exchange program for actinide measurement quality assurance (2001–2007)

Plutonium metal exchange programs operated by the Rocky Flats Plant were conducted from 1956–1989 to ensure quality and to compare measurements in a plutonium metal matrix. Los Alamos National Laboratory (LANL) re-established the program in 2001 to assess the quality of analytical chemistry capabilities that support special nuclear material characterization. It is the only program of its kind for the preparation and distribution of plutonium metal reference materials with a range of impurity contents to multiple laboratories for destructive measurements of elemental concentration, isotopic abundance, and both metallic and non-metallic impurity levels. This program provides independent verification of analytical measurement capabilities for each of the seven currently participating laboratories, and allows any technical problems with analytical measurements to be identified and corrected. This paper focuses on basic program elements and presents a summary of methods and results for plutonium, uranium, neptunium, and americium, measurements.     

Limitations of Tissue Analyses in Estimating the Initial Exposures to the Workers for Thorium, Uranium and Plutonium and Their Internal Dose Estimates

The present paper deals with the following questions: Can a piece of any tissue or organ obtained at autopsies and/or biopsies be analyzed to predict the organ and/or body burden, initial exposures, and the committed dose equivalents to the workers or retired workers from exposures to thorium, uranium, and plutonium and what are the consequences of using such materials in predicting the initial exposures and the dose estimates? Based on the studies of the distribution of uranium and thorium in former uranium miners and millers, the distribution of plutonium in general population, and several other studies dealing with the distribution of actinides in man, it is reasonable to state that the utilization of tissue analyses for estimating the initial exposure to the workers may have serious limitations. The regulatory agencies must restrict the conditional utilization of tissue analyses in estimating exposures to the workers for thorium, uranium, and plutonium.     

Determination of plutonium and uranium in the same aliquot by potentiometric titration

A potentiometric titration method was developed for the determination of plutonium and uranium in the same aliquot in nitric acid medium. Plutonium was first determined by oxidation to Pu/VI/ by fuming with conc. HClO₄. Pu/VI/ formed was reduced to Pu/IV/ with known excess of Fe/II/ and the excess Fe/II/ was titrated with standard K₂Cr₂O₇ to a potentiometric end point. Uranium in the same solution was determined by reduction to U/IV/ with Fe/II/ in conc. H₃PO₄ medium and titrating U/IV/ formed with standard K₂Cr₂O₇ using the potentiometric end point detection technique. For the quantity of plutonium and uranium each in the range of 3–5 mg per aliquot a precision of ±0.2% and ±0.4%, respectively, was obtained.     

Extraktionschromatographische Trennung von Plutonium(III), Uran(IV) und Uran(VI)

Zusammenfassung Eine extraktionschromatographische Trennung der Ionen Plutonium(III), Uran(IV) und Uran(VI) voneinander wird beschrieben. Tri-n-butylphosphat (TBP) auf einem Trägermaterial aus Polytrifluoromonochloroäthylen wurde als stationäre und Salpetersäure/Hydrazin als mobile Phase verwendet. Die Stabilität des Uran(IV), des Plutonium(III) und der Kolonne unter den Bedingungen der Trennung, der Einfluß der Salpetersäurekonzentration und der Elutionsgeschwindigkeit auf die Effektivität der Trennung, sowie das Verhalten anderer Lösungsbestandteile wurden untersucht. Über das extraktionschromatographische Verhalten des Uran(IV) wird erstmals berichtet. Die wenigen zur Ausführung der Trennung notwendigen Handgriffe sind einfach, was für das Arbeiten in Handschuhkästen von Vorteil ist.

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Extraction-chromatographic separation of plutonium(III), uranium(IV) and uranium(VI)

Summary An extraction-chromatographic separation of the ions plutonium(III), uranium(IV) and uranium(VI) from each other is described. Tri-n-butyl phosphate (TBP) on a carrier material made from polytrifluorochloroethylene was employed as the stationary phase while nitric acid/hydrazine served as the mobile phase. The stability of uranium(IV), of the plutonium(III) and the column under the conditions of the separation were studied, as well as the influence of the acid concentration and the elution rate, on the effectiveness of the separation, and also the behavior of other constituents of the solution. The extraction-chromatographic behavior of uranium(IV) is reported here for the first time.— The few manipulations necessary for the accomplishment of the separation are simple, which constitutes an advantage for the working in the glove box.

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Einige Experimente wurden währed eines Aufenthaltes bei der Firma Eurochemic in Mol/Belgien ausgeführt.     

Evolution of actinide partitioning with colloidal matter collected at PA “Mayak” site as studied by sequential extraction

Evolution of actinide partitioning to colloids upon subsurface migration in the vicinity of Karachay Lake (PA “Mayak”, Russia) was studied by micro- and ultrafiltration and sequential extraction. Colloidal matter was characterized by SEM-EDX, TEM and photon-correlation spectroscopy. Samples were collected from wells with different redox conditions i.e. from higly oxic to rather reducing. Under oxidizing conditions uranium and neptunium is readily washed out from colloids. Plutonium and americium are present in colloidal matter mainly as hard-soluble species. Under oxidizing conditions plutonium and americium are predominantly bound to organic/mineral fractions (carbonates, oxides and organically bound). Under reducing conditions plutonium and americium are present in immobile refractory fraction. It was also established that uranium and neptunium under reducing conditions behave similarly to plutonium. This phenomenon may be explained by the fact that under reducing conditions and at considerable concentrations of uranium and nitrite-ions these elements form low-soluble An(IV) forms.     

Comparing Branched versus Straight-chained Monoamide Extractants for Actinide Recovery

Separations of used nuclear fuel at the engineered scale have generally been completed using the Plutonium Uranium Redox Extraction (PUREX) process. The PUREX process uses tributyl phosphate (TBP) as an extractant to recover uranium and plutonium. While the TBP extractant has proven effective at recovering U and Pu at the engineered scale, TBP is potentially vulnerable to third phase formation and TBP degradation products (monobutyl and dibutyl phosphoric acids) which can complicate recovery of extracted metals from the organic phase. An alternative class of extractants, monoamides, has been considered for applications in thorium and uranium fuel cycles. When compared to TBP, monoamides tend to have higher separation factors for U or Pu from fission products, structural materials, and Th. This review summarizes the literature that explores actinide separations using monoamides by assessing the physiochemical properties between a broader library of branched and straight-chain monoamides than considered in previous reviews. An emphasis is placed on fine-tuning the selectivity of branched monoamides.     

Determination of uranium and plutonium in shielding concrete

The formation of plutonium radionuclides (^239+240Pu) from uranium was determined in dismounted shielding concrete from accelerator components. Plutonium and uranium fractions were separated by radioanalytical techniques and measured by -spectroscopy. The measurements are consistent with yield calculations based on transport and single particle codes. The yield of ^239+240Pu did not exceed the two-fold exemption limit given in the Swiss Radiation Protection Law, thus the plutonium content in shielding concrete should not cause problem for the environment.This revised version was published online in November 2005 with corrections to the Cover Date.     

Determination of plutonium isotope ratios at very low levels by ICP-MS using on-line electrochemically modulated separations

Electrochemically modulated separations (EMS) are shown to be a rapid and selective means of extracting and concentrating Pu from complex solutions prior to isotopic analysis by inductively coupled plasma mass spectrometry (ICP‐MS). This separation is performed in a flow injection mode, on‐line with the ICP‐MS. A three‐electrode, flow‐by electrochemical cell is used to accumulate Pu at an anodized glassy carbon electrode by redox conversion of Pu(III) to Pu (IV&VI). The entire process takes place in 2% (v/v) (0.46 M) HNO₃. No redox chemicals or acid concentration changes are required. Plutonium accumulation and release is redox dependent and controlled by the applied cell potential. Large transient volumetric concentration enhancements can be achieved. Based on more negative U(IV) potentials relative to Pu(IV), separation of Pu from uranium is efficient, thereby eliminating uranium hydride interferences. EMS‐ICP‐MS isotope ratio measurement performance will be presented for femtogram to attogram level plutonium isotope injections.     

Spectrophotometric determination of plutonium with chlorophosphonazo III

Summary Plutonium(IV) forms a Chlorophosphonazo III complex in 0.5–2M hydrochloric acid. Maximum absorbance occurs at 620 and 685 nm. Beer's law is obeyed over the range of 0–50g per 10 ml and the molar absorptivity is 3.7×10⁴ mol^–1 cm^–1 at 690 nm. Plutonium can be determined in the presence of fluoride, sulfate and phosphate. However, lanthanides, thorium, uranium and zirconium interfere seriously.

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Zusammenfassung Plutonium(IV) bildet in 0,5-bis 2-m Salzsäure mit Chlorphosphonazo III eine Komplexverbindung, deren Absorptionsmaxima bei 630 und 685 nm liegen. Bis 50 g/10 ml entspricht die Farbe dem Beer'schen Gesetz; die molare Extinktion bei 690 nm beträgt 3,7·10⁴l·Mol^–1·cm^–1. Plutonium kann damit in Gegenwart von F^–, SO₄ ^2– und PO₄ ^3– bestimmt werden. Lanthanide, Th, U und Zr stören jedoch ernstlich.

     

Precise coulometric determination of uranium,plutonium and americium-application to small samples

Summary Isotopic dilution followed by mass spectrometry is currently used for the determination of microquantities of actinides, but for this method it is necessary to prepare certified solutions of isotopic diluents. The isotopes used are very expensive and often available only in small quantities. New methods have been developed for the accurate and precise determination of small amounts of uranium, plutonium and americium. By using controlled-potential coulometry 0.5eq of uranium and plutonium can be determined with a precision of 0.1% (coefficient of variation). For americium a constant-current coulometric titration allows the determination of 1eq with a precision of 0.3%. The equipment, coulometric cells and procedures are described. The results obtained for standard materials and comparisons with results from other analytical methods are given.

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Genaue coulometrische Bestimmung von Uran, Plutonium and Americium; Anwendung auf kleine Proben

Zusammenfassung Isotopenverdünnung und nachfolgende Massenspektrometrie werden laufend für die Bestimmung kleiner Mengen von Actiniden verwendet; dazu ist es aber notwendig, genaue Lösungen von Isotopen zur Verdünnung herzustellen. Die dazu verwendeten Isotopen sind sehr teuer und oft nur in sehr kleinen Mengen zu haben. Für die genaue Bestimmung kleiner Mengen Uran, Plutonium und Americium wurden neue Methoden ausgearbeitet. Unter Verwendung der potential-kontrollierten Coulometrie lassen sich 0,5eq Uran und Plutonium mit einer Genauigkeit von 0,1% (Variations-Koeffizient) bestimmen. Gleichstromcoulometrische Titration ermöglicht die Bestimmung von 1eq Americium mit einer Genauigkeit von 0,3%. Einrichtung samt coulometrischer Zellen und Arbeitsweise wurden beschrieben. Die mit Standardproben erzielten Resultate wurden mit den Ergebnissen anderer Verfahren verglichen.

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Presented at the 8th International Microchemical Symposium, Graz, August 25–30, 1980.     

Sequential separation of Pu,Np, U and Am from highly radioactive Hanford waste by ion exchange methods

A simple, rapid method has been developed for the sequential separation of actinide elements from samples with high salt content such as those resulting from efforts to characterize Hanford storage tank waste. Actinides in 9M HCl solution are introduced into an anion exchange column. U(VI), Np(IV) and Pu(IV) are retained on the column while Am(III) passes through. Plutonium is eluted first, reductively; after which neptunium and then uranium are eluted with mixtures of HCl and HF. The Am(III) is purified by cation exchange in a nitric acid system.Pacific Northwest Laboratory is operated for U. S. Department of Energy by Battelle Memorial Institute under Contract DE-AC06-76RLO 1830.