Determination of uranium, thorium, and 20 other elements in high-purity tungsten by radiochemical neutron activation analysis

A radiochemical neutron activation analysis method for the determination of 22 elements in high-purity tungsten has been developed. For the assay of indicator radionuclides with long half-lives, the radiochemical separation was performed from HF/H₂O₂, HF/NH₄F and HCl/H₂SO₄ media by a combination of cation and anion exchange on a Dowex 50 W × 8 and Dowex 1 × 8 column. An effective removal of the matrix-produced radionuclides of W and Re was achieved. U was determined via ¹⁴⁰La, the daughter nuclide of the fission product ¹⁴⁰Ba. Limits of detection of 2 ng/g for U and 0.02 ng/g for Th can be achieved. For the other elements, the limits of detection are between 0.004 ng/g (Sc) and 200 ng/g (Sr). The elements Hf, Ta and Sb could be determined by instrumental neutron activation analysis. This method was applied to the analysis of two tungsten powder samples of different purity grade. The results and limits of detection are compared with those of other methods.     

Determination of uranium, thorium, and 20 other elements in high-purity tungsten by radiochemical neutron activation analysis

A radiochemical neutron activation analysis method for the determination of 22 elements in high-purity tungsten has been developed. For the assay of indicator radionuclides with long half-lives, the radiochemical separation was performed from HF/H₂O₂, HF/NH₄F and HCl/H₂SO₄ media by a combination of cation and anion exchange on a Dowex 50 W × 8 and Dowex 1 × 8 column. An effective removal of the matrix-produced radionuclides of W and Re was achieved. U was determined via ¹⁴⁰La, the daughter nuclide of the fission product ¹⁴⁰Ba. Limits of detection of 2 ng/g for U and 0.02 ng/g for Th can be achieved. For the other elements, the limits of detection are between 0.004 ng/g (Sc) and 200 ng/g (Sr). The elements Hf, Ta and Sb could be determined by instrumental neutron activation analysis. This method was applied to the analysis of two tungsten powder samples of different purity grade. The results and limits of detection are compared with those of other methods. Received: 28 July 1997 / Revised: 29 October 1997 / Accepted: 1 November 1997     

A neutron activation procedure for the determination of dissolved silver in sea water

A neutron activation procedure has been developed for the determination of silver in sea water. The element is preconcentrated by an anion-exchange procedure. The concentrate is submitted to irradiation with thermal neutrons. Silver-11Om is separated from other radionuclides by means of a conventional radiochemical separation scheme. The method gave a coefficient of variation of ± 10% at a silver level of 40 ng l^?1.     

Ultratrace characterization of AlSiCu sputter targets for Th,U and 35 other elements by neutron activation analysis

Instrumental and radiochemical neutron activation analysis has been applied to a comprehensive trace characterization of AlSiCu sputter targets. By instrumental neutron activation analysis via long-lived indicator radionuclides, up to 33 elements were assayed with detection limits between 0.01 and 200 ng·g^–1. The high activity of⁶⁴Cu and²⁴Na produced from the matrix significantly limits the instrumental performance via short- and medium-lived indicator dionuclides. For this reason, a radiochemical separation was developed based on adsorption of²⁴Na on hydrated antimony pentoxide and extraction of⁶⁴Cu by diethylammonium diethyldithiocarbamate from HCl medium. By this radiochemical method, As, Ga, K, La, Mn, Mo, Re, Sb, U and W could be assayed via medium-lived radionuclides and the achievable limits of detection were between 0.1 and 25 ng·g^–1. Further improvement of detection limits for U and Th was achieved by a selective radiochemical separation of²³⁹Np and²³³Pa on a Dowex 1×8 column in HF and HF/NH₄F medium providing limits of detection for U and Th of 0.06 and 0.02 ng·g^–1, respectively. These techniques were applied to the analysis of two AlSiCu sputter target materials. Results are compared with those of glow discharge mass spectrometry.     

Radiochemical determination of Mo in pure tungsten

A radiochemical neutron activation technique for Mo determination in high purity tungsten, based on some specific properties of Mo and W radionuclides has been developed. Al₂O₃ powder has been used as a sorbent. An estimation of the Mo content was carried out via the selectively separated^99mTc daughter radionuclide. Limit of detection was 10 ng g^–1.     

The determination of zirconium in animal tissues by neutron activation and γ-spectrometry

A neutron activation method has been developed for determining microgram and submicrogram quantities of zirconium in animal tissue. The procedure uses phosphate to aid in the separation of zirconium from interfering radio-isotopes. Tissues are dried, sealed in quartz vials, irradiated at a high flux, and wet-ashed; the zirconium is precipitated as ZrO(H₂PO₄), redissolved, and precipitated as BaZrF₆. This procedure effectively removed interfering radioactive elements. Chemical oxidation and the simple separation procedure were checked by radiotracer experiments, and by processing tissues to which known quantities of zirconium had been added. The detection limit of the method for a 100-h irradiation at 1 × 10¹⁴ n cm^-2 s^-1 followed by radiochemical processing is 10 ng, based on 2 σ counting statistics. The error is estimated to be ± 5–10%.     

A simplified method for simultaneous quantitation of alkylphenols and alkylphenol ethoxylates in meat and fish using high-performance liquid chromatography with fluorescence detection

Nonylphenol (NP), octylphenol (OP), nonylphenol monoethoxylate (NP₁EO) and nonylphenol diethoxylate (NP₂EO) are products of the biodegradation of alkylphenol polyethoxylates (AP _n EO) which are used worldwide as detergents and surfactants. NP and OP are categorized as definitely endocrine disruptors. 2,4-Tert-butylphenol (BP) is extensively used for anti-oxidant of rubber and plastics. This work proposed a simple and stable method for simultaneously determining the concentration of NP, OP, BP, n-NP₁EO and n-NP₂EO in meat and fish, without requiring the complex pretreatments of current methods. This study used liquid extraction with acetonitrile and hexane and solid extraction using Florisil, in that order to pretreat samples. The sample solutions were analyzed to identify NP, OP, BP, n-NP₁EO and n-NP₂EO by HPLC with fluorescence detection. The mean recoveries were 85.3?±?3.32% for OP, 87.5?±?6.01% for BP, 90.9?±?4.72% for NP, 86.4?±?4.81% for n-NP₂EO and 90.9?±?4.84% for n-NP₁EO. The average coefficients of variation were about 6%. The method's detection limits were 5.4?ng?g^?1 for OP, 5.2?ng?g^?1 for BP, 8.9?ng?g^?1 for NP, 8.7?ng?g^?1 for n-NP₂EO and 8.1?ng?g^?1 for n-NP₁EO. This work analyzed 5 kinds of usual foodstuffs of meat and fish that are frequently consumed by residents of Taiwan. All of these samples contained NP, but not detectable levels n-NP₁EO. Only salmon was contaminated with n-NP₂EO. The NP level was highest in cod (198.41?±?129.34?ng?g^?1, wet weight). The fried chicken had the highest BP level (48.0?±?41.3?ng?g^?1, wet weight), and the uncooked chicken had the highest OP level (66.6?±?53.0?ng?g^?1, wet weight).     

The determination of tellurium in weathered outcrop,mineralized and barren rock

Sensitive and specific methods have been developed for the determination of tellurium in a wide variety of rocks and minerals. X-ray fluorescence is used for concentrations above 1 μg g^-1 and carbon furnace atomization a.a.s. for concentrations of 0.01–1μg g^-1. The tellurium is separated by precipitation as elemental tellurium after dissolution in acid; alternative dissolution procedures have been investigated.     

Thermal stabilization of inorganic and organically- bound tellurium for electrothermal atomic absorption spectrometry

The thermal stabilization of inorganic tellurium(IV) and organically-bound tellurium for electrothermal atomic absorption spectrometric determination of the element was studied with the use of the isotope tellurium-127m. Of the 19 metals and potassium iodide tested, 15 metals had a stabilizing effect on inorganic tellurium; among the 9 metals tested with organically-bound tellurium, only 3 exhibited an effect. The most effective metals for stabilizing inorganic tellurium were cadmium, copper, palladium, platinum and zinc, while the best agents for stabilization of organically-bound tellurium were silver, palladium and platinum; in the presence of palladium and platinum, tellurium in both forms could be heated in the graphite tube to 1050°C without losses. Attempts were made to determine tellurium in human whole blood and garlic, but the concentrations were found to be below the detection limits of 3 ng ml^-1 and 140 ng g^-1, respectively.     

EPR evidence for 17O− on molybdenum oxide supported by silica-gel

The EPR spectrum of ¹⁷O^? on partially reduced molybdenum oxide supported on silica-gel has been observed following adsorption of N₂O at room temperature. The spectrum is chracterized by g_⊥=2.019 and g_|=2.002 with a_|¹⁷O^?=96±1 G and a_|⁹⁵MO,⁹⁷MO=7.5±0.5 G. The O ^?ion appears to undergo exchange with oxide ions at the surface.     

Rapid activation analysis of trace vanadium in tissue using 3.8-minute vanadium-52

Submicrogram amounts of vanadium in rat liver tissue have been analyzed by rapid activation analysis. A 5-min radiochemical separation coupled with γ-ray spectrometry permitted utilization of the 3.8-min vanadium-52 radioisotope. With this procedure the lower limit of detection at a thermal neutron flux of 10¹² n/cm²/sec was about 3·10^-9 g of vanadium.     

Determination of Platinum in Plant Samples by Voltammetric Analysis

A voltammetric method using solid electrode of glassy carbon as a working electrode is describes for determination of platinum in grass samples taken from the vicinity of a motorway. Standard addition was used for quantitative analysis of Pt in 0.05 M H₂SO₄. The analyte concentration in plant tissues reached 19.1±1.6 ng g^?1 for leaves of samples collected from the least polluted areas, and up to 136±2 ng g^?1 for roots of sample taken from the area of heavy road‐traffic.     

The determination of molybdenum in geological samples by Neutron Activation Analysis

A metal-silicate extraction technique combined with neutron activation analysis has been developed to determine molybdenum in geological samples. The samples are equilibrated with Femetal powder at high temperatures. Molybdenum is completely extracted into the metal phase because of very reducing conditions in the furnace. The metal spherule is separated from the silicates, irradiated and dissolved in an acid solution. The molybdenum is precipitated as a sulfide and the precipitate is dissolved in aqua regia and counted on a Ge/Li/detector. The radiochemical yield is obtained by irradiation of the solution. The method avoids production of⁹⁹Mo from induced fission of²³⁵U by performing the metal-silicate separation before irradiation. The precipitation step may be necessary to remove the high background from the decay of⁵⁹Fe. Mo concentrations down to 15 ng/g have been obtained using this method.     

Radiochemical scheme for the determination of molybdenum and uranium in biological materials by NAA

A new universal radiochemical separation scheme for selective and quantitative isolation of molybdenum and neptunium (formed from uranium), from neutron irradiated biological materials has been elaborated. The procedure is based on ion exchange and extraction chromatography with final fixation of molybdenum on a column with -benzoinoxime supported on Bio-Beads SM2 and neptunium on Dowex 1-X8 [No ₃ ^– ]. The separated elements are quantified using gamma-spectrometric measurements. The new NAA method is able to overcome problems associated with high contents of phosphorous in some samples and assures detection limits better than 3 ppb for both elements. The validity of the proposed scheme has been demonstrated by the analysis of several CRM's.     

Measurements of activation cross-sections for the 101Ru(n,p)101Tc reaction for neutrons with energies between 13 and 15 MeV

In this study, activation cross-sections were measured for the ¹⁰¹Ru(n,p)¹⁰¹Tc reaction at three different neutron energies from 13.5 to 14.8 MeV. The fast neutrons were produced via the ³H(d,n)⁴He reaction on K-400 neutron generator. Induced gamma activities were measured by a high-resolution gamma-ray spectrometer with high-purity germanium detector. Measurements were corrected for gamma-ray attenuations, random coincidence (pile-up), dead time and fluctuation of neutron flux. The data for ¹⁰¹Ru(n,p)¹⁰¹Tc reaction cross-sections are reported to be 15.7 ± 2.0, 18.4 ± 2.7 and 22.0 ± 2.4 mb at 13.5 ± 0.2, 14.1 ± 0.2, and 14.8 ± 0.2 MeV incident neutron energies, respectively. Results were compared with the previous works.     

Multi-element characterization of high-purity titanium dioxide by neutron activation analysis

A radiochemical neutron activation analysis method for the determination of 34 elements in titanium dioxide has been developed. For the assay of indicator radionuclides with short and with long half-lives, the radiochemical separation was performed by anion exchange on a Dowex 1 × 8 column and by combination of cation and anion exchange on a Dowex 50W × 8 and a Dowex 1 × 8 column from HF- and HF/NH₄F-medium, respectively. With both separation modes, a selective removal of the matrix-produced radionuclides ⁴⁶Sc, ⁴⁷Sc and ⁴⁸Sc was achieved. A selective extraction of copper with dithizone from 15 mol/L HF enabled counting the intensive but unspecific 511-keV rays of ⁶⁴Cu for the determination of Cu. The limits of detection achieved were between 0.004 ng/g for Sm and 0.8 μg/g for Sn (via ¹²⁵Sb). The elements La, Mn and Th were determined by instrumental neutron activation analysis only. These techniques were applied to the analysis of two titanium dioxide samples of different purity grade. The results and limits of detection are compared with those of other methods.     

Determination of chlorine in silicate rocks by neutron activation analysis

A simple radiochemical neutron activation analysis scheme has been developed for the determination of chlorine in silicate rocks. The method involves a 15-min thermal neutron irradiation of rock powder followed by a quick separation of ³⁸Cl as AgCl, and Ge(Li) spectrometry. Chemical yield, normally ranging between 95% and 100%, is monitored gravimetrically through the recovery of AgCl. The procedure has been tested on several geochemical standards to assess its accuracy and precision. The values obtained for standard rocks agree with the literature values. At the 100-ppm level, the analytical precision for chlorine is within ±5% (2σ).     

Ein Trennverfahren zur Bestimmung von Ag, Cd, Hg und Zn in biologischem Material durch radiochemische Neutronenaktivierungsanalyse

Zusammenfassung Es wurde ein einfaches Trennverfahren für die radiochemische NAA von biologischem Material entwickelt, mit dem aus einem komplexen Nuklidgemisch die Indicator-Radionuklide ^110mAg, ¹⁹⁸Au, ¹¹⁵Cd, ²⁰³Hg und ⁶⁵Zn als eine Gruppe mit Ausbeuten >99% abgetrennt werden können. Besonders geeignet ist dieses Verfahren für die Trennung des ²⁰³Hg von ⁷⁵Se und ⁶⁵Zn von ⁴⁶Sc, die sich bei einer gammaspektrometrischen Messung in der instrumentellen NAA gegenseitig stören. Gleichzeitig können die Nachweisgrenzen für Ag, Au und Cd wesentlich gesteigert werden. Das Verfahren basiert auf dem Aufschluß der bestrahlten Probe in einem Gemisch von HNO₃, HCl und H₂O₂, und auf der Trennung von Ag, Au, Cd, Hg und Zn an Dowex 1X8 aus 1,5 M salzsaurer Probelösung. Die Leistungsfähigkeit dieses Verfahrens wurde an Beispielen der Analyse von Flechten und verschiedenen Pilzarten demonstriert. Bei den verwendeten experimentellen Bedingungen liegen die Nachweisgrenzen in der Größenordnung von 10 ng/g.

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A separation procedure for the determination of Ag, Cd, Hg and Zn in biological material by radiochemical neutron activation analysis

Summary A simple separation procedure for the determination of Ag, Au, Cd, Hg and Zn in biological material by radiochemical neutron activation analysis was developed. It enables the separation of the indicator radionuclides ^110mAg, ¹⁹⁸Au, ¹¹⁵Cd, ²⁰³Hg and ⁶⁵Zn in a group with yields >99% and is well suited for the separation of ²⁰³Hg from ⁷⁵Se and ⁶⁵Zn from ⁴⁶Sc. The separation of these radionuclides is often necessary because of the occurrence of instrumental interferences in the instrumental neutron activation analysis. Simultaneously, the limits of detection for Ag, Au and Cd can significantly be improved. The method is based on the decomposition of the sample in the mixture of HNO₃/HCl/H₂O₂ and on the separation of Ag, Au, Cd, Hg and Zn on Dowex 1X8 from a sample solution being 1.5 M with HCl. The applicability of this method is demonstrated by the analysis of lichens and several kinds of fungi. For the experimental conditions used, the limits of detection are of the order of magnitude of 10 ng/g.

     

Radiochemical separation of110mAg,210Pb,127Te and131I from aqueous nitric acid solution by bis-2-(butoxyethyl ether)

A bis-2-(butoxyethyl ether) (DBC) solvent extraction method has been developed for the radiochemical separation of^110mAg,²¹⁰Pb,¹²⁷Te and¹³¹I in varying concentrations of aqueous HNO₃. Various factors were examined to determine the optimum conditions of extraction. The effect of various masking agents has been studied. The extraction of¹³¹I is enhanced to 99% at 2.4M HNO₃ in the presence of KSCN.¹³¹I was stripped into aqueous sodium hydroxide from the oxygenated organic extractant. The method was then applied for the recovery of¹³¹I from neutron irradiated tellurium metal. The mechanism and reactivity of DBC with metal ions is described.     

Separation of carrier-free 64,67Cu radionuclides from irradiated zinc targets using 6-tungstocerate(IV) gel matrix

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.