Thermal decomposition of ammonium uranium fluoride

Thermal decomposition of uranium double fluoride in a screw reactor in the temperature range of 250–500 °C is presented. Using integral reactor relation, kinetic parameters are discussed in terms of the shrinking core grain model. Arrhenius global activation energy is also determined.     

Radiochemical determination of fission products of uranium

An analysis has been elaborated to determine the long-living γ-emitting fission products of uranium. It consists of a sodium bisulphate melt of the fission product solution or the U-fuel, followed by liquid-liquid extractions. Afterwards the isotopes are absolutely counted with a standardized 3″×3″ NaI crystal. The total γ-spectrum of the original fission product solution, taken with a NaI crystal or a Ge−Li detector, is also analyzed mathematically by mixed γ-spectrometry. From a short post-irradiation of the fission product solution the concentrations of both²³⁵U and²³⁸U are determined. The absolute amount of fission products related to the U-concentration allows the calculation of the percent atomic burn-up, the irradiation time, the cooling period, the flux of the reactor and the original degree of enrichment of the uranium. Research associate of the I. I. K. W.     

X射线荧光法测定天然铀产品中铀含量的不确定度评定

利用X射线荧光法测定天然铀产品中铀含量,对测定结果的不确定度进行评定.建立了数学模型,分析了不确定度来源,计算合成标准不确定度和扩展不确定度.结果表明,标准曲线拟合、测量重复性、天平称量和标准样品量值对测定结果影响较大,当样品中铀的质量分数为84.736％时,其扩展不确定度U=0.078％(k=2).     

The determination of uranium in alloy systems

A procedure is described for the determination of the uranium content of metallurgical alloys containing this element as a minor constituent. The uranium is first separated from the sample solution by precipitation as uranyl ammonium phosphate in the presence of ethylenediamine-totra-acetic acid. By this means the uranium is separated from many elements including iron, chromium, copper, nickel, vanadium, cerium, ncodymium and bismuth. Tho uranyl ammonium phosphate precipitate is dissolved in hydrochloric acid and the resulting solution is passed through a lead reductor. The tetravalent uranium is titrated with a standard cerie sulphate solution, using ferroin as the indicator. This procedure has proved very suitable for the analysis of bismuthuranium binary alloys containing uranium in amounts up to approximately 20%.     

Thermal behavior and pyrolysis products of modified organo-layered silicates as intermediates for in situ polymerization

A systematic study on organo-layered silicate intermediates used for preparing in situ polyethylene nanocomposites was performed by pyrolysis–gas chromatography/mass spectrometry and thermogravimetric analysis. The type and composition of the pyrolysis products gave useful information about mechanism of thermal degradation. The combination of pyrolysis and thermal decomposition data allowed us to describe the evolution of the organoclay structure after the reactive pretreatment steps with alkylaluminoxane cocatalyst and zirconocene or bis(imino)pyridine iron precatalyst, respectively. A proof of the formation of heterogeneous organoclay-immobilized catalyst was obtained.     

Thermal and kinetic analysis of uranium salts

Thermal decomposition of U(C₂O₄)₂·6H₂O was studied using TG method in nitrogen, air, and oxygen atmospheres. The decomposition proceeded in five stages. The first three stages were dehydration reactions and corresponded to removal of four, one, and one mole water, respectively. Anhydrous salt decomposed to oxide products in two stages. The decomposition products in nitrogen atmosphere were different from those in air and oxygen atmospheres. In nitrogen atmosphere UO_1.5(CO₃)_0.5 was the first product and U₂O₅ was the second product, while these in air and oxygen atmospheres were UO(CO₃) and UO₃, respectively. The second decomposition products were not stable and converted to stable oxides (nitrogen: UO₂, air–oxygen: U₃O₈). The kinetics of each reaction was investigated with using Kissinger–Akahira–Sunose and Flynn–Wall–Ozawa methods. These methods were combined with modeling equations for thermodynamic functions, the effective models were investigated and thermodynamic values were calculated.     

Extraction behavior of uranium,plutonium and some fission products with gamma-irradiated N,N′-dialkylamides

The extraction behavior of uranium(VI), plutonium(IV) and fission products like zirconium, ruthenium and europium from 3.5M nitric acid medium with gamma-irradiated dibutyl derivatives of hexanamide (DBHA), octanamide (DBOA) and decanamide (DBDA) in dodecane has been investigated as a function of absorbed dose up to 184 MRads. The results indicate that the K_d value for extraction of uranium(VI) decreases gradually, while K_d for extraction of plutonium(IV) decreases rapidly with dose up to 35 MRads, increasing thereafter with dose, indicating synergistic effects of radiolytic products at higher doses. Ruthenium and europium are not extracted in the entire dose range up to 184 MRads, while extraction of zirconium(IV) increases steadily up to 50 MRads and increases radiply thereafter, indicating synergistic effect of radiolytic products similar to that of plutonium(IV) beyond a dose of 50 MRads. The extractability of uranium(VI) and plutonium(IV) with 1M dibutyl decanamide (DBDA) in dodecane was studied for uranium loading up to 75 mg/ml and plutonium loading up to 3 mg/ml. The percent extraction was found to vary from 91 to 71 for uranium and 95 to 89 for plutonium, respectively. Quantitative stripping of uranium can be achieved with 0.01M nitric acid and plutonium with 0.5M nitric acid and 0.05M hydroxylamine soluton in two steps from an organic phase loaded with 53.2 mg/ml of uranium.     

Thermal and kinetic analysis of uranium salts

The thermal decomposition kinetics of UO₂C₂O₄·3H₂O were studied by TG method in a flowing nitrogen, air, and oxygen atmospheres. It is found that UO₂C₂O₄·3H₂O decomposes to uranium oxides in four stages in all atmosphere. The first two stages are the same in the whole atmosphere that correspond to dehydration reactions. The last two stages correspond to decomposition reactions. Final decomposition products are determined with X-Ray powder diffraction method. Decomposition mechanisms are different in nitrogen atmosphere from air and oxygen atmosphere. The activation energies of all reactions were calculated by model-free (KAS and FWO) methods. For investigation of reaction models, 13 kinetic model equations were tested and correct models, giving the highest linear regression, lowest standard deviation, and agreement of activation energy value to those obtained from KAS and FWO equations were found. The optimized value of activation energy and Arrhenius factor were calculated with the best model equation. Using these values, thermodynamic functions (??H ^*, ??S ^*, and ??G ^*) were calculated.     

Thermal and kinetic analysis of uranium salts

In this study the thermal decomposition kinetics of uranyl acetate dehydrate [UO₂(CH₃COO)₂·2H₂O] were studied by thermogravimetry method in flowing nitrogen, air, and oxygen atmospheres. Decomposition process involved two stages for completion in all atmosphere conditions. The first stage corresponded to the removal of two?moles of crystal water. The decomposition reaction mechanism of the second stage in nitrogen atmosphere was different from that in air and oxygen atmospheres. Final decomposition products were determined with X-ray powder diffraction method. According to these data, UO₂ is the final product in nitrogen atmosphere, whereas U₃O₈ is the final product in air and oxygen atmospheres. The calculations of activation energies of all reactions were realized by means of model-free and modeling methods. Kissinger?CAkahira?CSunose (KAS) and Flynn?CWall?COzawa (FWO) methods were selected for model-free calculations. For investigation of reaction models, 13 kinetic model equations were tested. The model, which gave the highest linear regression, the lowest standard deviation, and an activation energy value which was close to those obtained from KAS and FWO equations, was selected as the appropriate model. The optimized value of activation energy and Arrhenius factor were calculated using the selected model equation. Using these values, thermodynamic functions (??H*, ??S*, and ??G*) were calculated.     

On the uranium content in some technogenic products potential environmental pollutants

The uranium contents in phosphorites from North Africa, products of their processing (H₃PO₄, superphosphates, phosphogypsum), lignites from South Bulgaria and products of their burning, copper ores and concentrates have been determined by instrumental and radiochemical NAA. An evaluation of the contribution of the phosphoric fertilizers to the uranium content of soil, plants, breeding stock and man has been done.     

Factors influencing the sorption and migration behavior of uranium in shale

Journal of Radioanalytical and Nuclear Chemistry - The sorption of U(VI) on shale has been experimentally investigated as a function of pH, initial uranium concentration, rock particle size and...     

Defluorination behavior and mechanism of uranium dioxide

The residual fluorine in ammonium uranyl tricarbonate (AUC) cannot be removed, while a large part of residual fluorine in ammonium diuranate (ADU) can be removed, when AUC and ADU are decomposed and reduced under dry hydrogen atmosphere. UO₂ was prepared by decomposing and reducing AUC and ADU in dry hydrogen atmosphere. The defluorination kinetics of UO₂ at 500–700°C in atmosphere of 50% H₂-50% H₂O was investigated. The results show that the defluorination kinetics supports the Lindman's assertion that the residual fluorine forms a solid-solution in UO₂.     

Thermal behaviour of uranium(VI) complexes

The solid-state syntheses of complexes of uranyl acetate dihydrate andN-phenylthiourea have been attempted by heating various stoichiometric mixtures of the reactants directly in a DSC and in a TA apparatus. Both the DSC and the TG results indicate that only the 1∶1 adduct is formed, independently of the molar ratios of the reactants. It appears that the reaction is complete only with a large excess ofN-phenylthiourea, in agreement with IR data.     

Polarographic behavior of uranium(VI) in malonic acid media determination of uranium in plutonium

The polarographic behavior of the uranium-malonate complex was investigated over the pH range 1.1–6.5. A reversible, one-electron wave was obtained. Below pH 4.9, the rate of disproportionation is nearly instantaneous and gives rise to a pseudo uranium(VI)-uranium(IV) reduction. Above pH 4.8 the concentration of uranium(V) is stable with respect to disproportionation. The half-wave potential is pH-dependent below pH 4.9, but it is independent of the malonate concentration above O.1 M. The diffusion current constant is 2.78 for the conditions described. A procedure for the determination of uranium in plutonium was developed for uranium concentrations greater than 225 p.p.m. Of 21 common impurities found in plutonium metal, only Cu, Fe, Pb, Sb and Ti cause significant interference ; titanium can be removed by ion exchange, and the other interferences by mercury cathode electrolysis.     

Thermal decomposition products of polypropylene

Isotactic polypropylene was decomposed under vacuum at 360, 380, and 400°C, and the volatile products from C₁ to C₁₂ hydrocarbons were analyzed by gas chromatography. The formation of the main products is discussed on the basis of a free-radical mechanism in which intramolecular radical transfer is assumed to play an important role. The mechanism of the formation of a number of products suggested by previous workers is criticized on the basis of the results of a more comprehensive analysis of this investigation.     

Thermal decomposition products of polyisobutylene

Polyisobutylene was decomposed at 325, 345, and 365°C under vacuum, and the volatile products were trapped by using liquid nitrogen. The products, C₁–C₂₄ hydrocarbons, were analyzed by gas chromatography. The formation of the main products is discussed on the basis of a free-radical mechanism. Intramolecular radical transfer can account for the production of most fragments including dimers, trimers, tetramers, and so on, of isobutylene.     

Thermal decomposition products of polyethylene

Decomposition products of polymers have been determined by many investigators, but the results are often conflicting because of difficulties in analyzing a large number of products. A comprehensive analysis of the volatile thermal decomposition products of high-density polyethylene has been made with the latest techniques in gas chromatography. The formation of products is explained on the basis of free-radical mechanism. The predominant process in the formation of volatiles appears to be intramolecular transfer of radicals, in which isomerization by a coiling mechanism plays an important role in determining the relative quantities of each product.     

Gas-chromatographic technique for rapid isolation of uranium fission products

Summary A gas-chromatographic technique for a rapid separation of fission iodine or bromine from the other elements formed in nuclear fission was developed. Recoil-formed, volatile methyl bromide and methyl iodide were isolated within 1 min after the end of irradiation. An extension of this technique to other elements and to other nuclear reactions should be possible.The -ray spectra of both halogen fractions were measured. A dominating -ray at 0.79 MeV and a weaker -ray at 0.51 MeV were assigned to ⁸⁸Br (half life 16 sec). No -ray could be unambiguously attributed to ¹³⁷I (24 sec), a fact which makes unlikely the presence of highly intensive peaks in the -ray spectrum of this isotope. Further details of the spectra are discussed.

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Zusammenfassung Eine gaschromatographische Methode zur schnellen Isolierung von Spaltjod oder Spaltbrom aus dem Gemisch der bei der Kernspaltung entstehenden Elemente wurde entwickelt. Mittels Spaltrückstoß gebildetes, flüchtiges Methylbromid oder Methyljodid wurde innerhalb 1 min nach Bestrahlungsende isoliert. Die Methode sollte auf andere Elemente und andere Kernreaktionen übertragbar sein.-Spektren der beiden Halogenfraktionen wurden gemessen und ergaben für ⁸⁸Br (Halbwertszeit 16 sec) eine dominierende Linie bei 0,79 MeV und eine schwache Linie bei 0,51 MeV. In der Jodfraktion wurde keine -Linie beobachtet, die man eindeutig ¹³⁷J (24 sec) hätte zuordnen können, was sehr intensive Peaks im Spektrum dieses Isotops unwahrscheinlich macht. Weitere Einzelheiten der Spektren werden diskutiert.

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Dedicated to Prof. Dr. F. Strassmann on his 65th birthday.     

Thermal behavior of poly-p-xylylene-m-carborane

Thermal analysis, infrared spectroscopy, and gel-permeation chromatography studies were undertaken to determine the behavior of poly(p-xylylene-m-carborane) at elevated temperature. Results show that the polymer softened at about 200°C, probably because of polymorphism. Chlorine atoms from chain ends also ruptured at this temperature. This initiated subsequent hydrogen abstraction and thermal oxidation reactions that resulted in the decomposition of the polymer. The process of degradation closely parallels the thermal oxidation of polybenzyl and other polymers with readily activated methylene groups. The volatile products that formed at 300 and 400°C were produced because of the cleavage of methylene groups and their oxidation products. Larger polymer segments containing phenylene and m-carborane groups were evolved at higher temperatures. Some crosslinking occurred when the polymer was heated in air at temperatures above 200°C. The degree of polydispersity of the polymer fraction that remained soluble in organic solvents increased with corresponding increase of temperature.