Determination of plutonium in biological materials by extraction and liquid scintillation counting
About: This article is published in Analytical Chemistry.The article was published on 1970-03-01. It has received 166 citations till now. The article focuses on the topics: Liquid scintillation counting & Extraction (chemistry).
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TL;DR: A nose-only inhalation exposure chamber in which fresh aerosol is flowed past each exposure port and exhaled air is immediately exhausted, which allows all animals in the chamber to be exposed to the same aerosol concentration.
Abstract: We have designed a nose-only inhalation exposure chamber in which fresh aerosol is flowed past each exposure port and exhaled air is immediately exhausted. This allows all animals in the chamber to be exposed to the same aerosol concentration. In tests comparing initial lung burdens (ILB) of animals exposed in a standard chamber with those of animals exposed in the flow-past chamber, coefficients of variation in ILBs were significantly smaller for the latter.
157 citations
TL;DR: In this paper, a laser-excited atomic fluorescence flame spectrometry with a pulsed nitrogen laser pumped tunable dye laser has been investigated with respect to analytical figures of merit, especially in terms of improvement of detection limits.
Abstract: Laser-excited atomic fluorescence flame spectrometry with a pulsed nitrogen laser pumped tunable dye laser has been investigated with respect to analytical figures of merit, especially in terms of improvement of detection limits. The detection limits for 19 elements in an air-acetylene flame and for 5 elements in a nitrous oxide-acetylene flame are evaluated in the cases of both resonance and nonresonance atomic fluorescence lines. The detection limits obtained have been improved about 10 to 200 times. Detection limits for many elements excited by the frequency doubled dye laser output are reported for the first time. Now, most elements examined can be detected at the ng ml/sup -1/ (ppB) level or less with analytical curve linearities of over five orders of magnitude. Improvement of the detection limits was achieved mainly by expanding the diameter of the laser beam to illuminate a larger analyte volume in the flame and by using a low dispersive spectrometric system. The optical arrangement employed reduced the scatter signal and improved the signal-to-noise ratio (SNR). Although a low dispersive spectrometric system (spectral bandwidth of ..delta..lambda/sub M/) was employed, the spectral resolution of the system was determined by the spectral bandwidth of the laser, ..delta..lambda/sub L/(..delta..lambda/sub L/ muchmore » less than ..delta..lambda/sub M/). Conditions for optimizing analytical results are discussed. The results indicate that laser-excited atomic fluorescence spectrometry is potentially superior to atomic absorption spectrometry, atomic emission flame spectrometry, atomic emission induction coupled plasma spectrometry, and conventional source atomic fluorescence spectrometry, in terms of analytical figures of merit.« less
97 citations
TL;DR: It is postulated that the deposition of U on trabecular endosteal surfaces will induce osteosarcoma(s) following prolonged exposure to 233U or 232U.
Abstract: The distribution, retention, and excretion of 233U were measured in seven beagles injected intravenously with 2.8 /zCi 233U(VI)/kg (-3 mg/dog) in citrate buffer and sacrificed at times ranging from 1 to 726 days postinjection (PI). The concentration of U in plasma decreased rapidly, and for the first 24 hr PI could be described by a triphasic exponential equation with half-times of 0.92, 46, and 315 min. The uranium in the blood at 5 min PI was present as either a protein (transferrin-albumin) or a carbonate/bicarbonate complex. Up to 60% of the injected U was excreted during the first day, most of it in the urine. Whole-body retention was 17% at 7 days, 10% at 94 days, 7.6% at 1 year, and less than 5% at 2 years PI. Except for the kidney, only a small fraction of the injected U was retained in soft tissues. At 1 day PI, the liver contained 1.1% of the injected U and its subcellular distribution was similar to that seen with Pu(IV). At 1 day PI, 7.7% of the U was found in the skeleton; this amount decreased with a biological half-life of 883 days. Initially, U was deposited nonuniformly on bone surfaces with areas of intense hot spots adjacent to areas with intermediate and low concentrations. At later times redistribution and/or diffusion of U into the bone volume produced a deposition pattern intermediate to that of 239Pu (surface) and 226Ra (volume). The heterogeneity of surface deposits persisted, and isolated segments of the trabecular bone showed intense surface deposits at times greater than 1 year PI. Twenty-two percent of the injected U was found in the kidneys at 1 day PI with high concentrations localized in the proximal tubules. The initially high concentration of U in this organ was correlated with extensive diuresis and a persistent elevation in blood urea nitrogen. Damage to proximal tubules was attributed primarily to chemical toxicity but was aggravated by simultaneous a irradiation. It is postulated that the deposition of U on trabecular endosteal surfaces will induce osteosarcoma(s) following prolonged exposure to 233U or 232U.
77 citations
TL;DR: It is suggested that oxidation of UO2 to UO3 occurs followed by the formation of uranyl ion in blood plasma and lung fluid as well as in aqueous suspension.
Abstract: 233UO2 and 233UO2(NO3)2 in aqueous suspension have been administered to rats by pulmonary intubation. The 233U associated with the fraction of the 233UO2 less than 4 nm in diameter translocates from lungs to blood at the same rapid rate as 233U from 233UO2(NO3)2. Identical reactions with blood plasma and lung fluid were observed whether the 233U was administered as less than 4 nm 233UO2 particles or 233UO2(NO3)2. It is suggested that oxidation of UO2 to UO3 occurs followed by the formation of uranyl ion. In blood plasma, approximately 50 per cent of the 233U is bound to transferrin, 25 per cent to citrate and 25 per cent on bicarbonate.
67 citations
TL;DR: In vitro solubility tests were useful, simple and easily applied to individual materials potentially inhaled by humans and suggested the dominant role of mechanical processes in PuO2 clearance from the lung.
Abstract: Dissolution characteristics of mixed-oxide nuclear fuels are important considerations for prediction of biological behavior of inhaled particles. Four representative industrial mixed-oxide powders were obtained from fuel fabrication enclosures. Studies of the dissolution of Pu, Am and U from aerosol particles of these materials in a serum simulant solution and in 0.1M HCl showed: (1) dissolution occurred at a rapid rate initially and slowed at longer times, (2) greater percentages of U dissolved than Pu or Am: with the dissolution rates of U and Pu generally reflecting the physical nature of the UO2-PuO2 matrix, (3) the temperature history of industrial mixed-oxides could not be reliably related to Pu dissolution except for a 3-5% increase when incorporated into a solid solution by sintering at 1750 degrees C, and (4) dissolution in the serum simulant agreed with the in vivo UO2 dissolution rate and suggested the dominant role of mechanical processes in PuO2 clearance from the lung. The rapid initial dissolution rate was shown to be related, in part, to an altered surface layer. The advantages and uses of in vitro solubility data for estimation of biological behavior of inhaled industrial mixed oxides, such as assessing the use of chelation therapy and interpretation of urinary excretion data, are discussed. It was concluded that in vitro solubility tests were useful, simple and easily applied to individual materials potentially inhaled by humans.
65 citations
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52 citations
TL;DR: A new method for the determination of base ratios of nucleic acids has been developed using gas-liquid chromatographic analysis of the purines and pyrimidines arising on perchloric acid hydrolysis of the nucleic acid.
40 citations
TL;DR: An accurate and simple procedure for the determination of plutonium in biological materials was developed in this paper, where concentrated urine, or a solution of bone ash, is made at least 1M in H/sub 2/SO/sub 4/, and plutonium is extracted with a mixture of C/sub 18/ to c/sub 23/ highly branched primary amines in xylene Plutonium is then extracted from the organic phase with 8M HCl, and measured by alpha counting (auth)
Abstract: An accurate and simple procedure for the determination of plutonium in biological materials was developed Concentrated urine, or a solution of bone ash, is made at least 1M in H/sub 2/SO/sub 4/, and plutonium is extracted with a mixture of C/sub 18/ to C/sub 23/ highly branched primary amines in xylene Plutonium is then extracted from the organic phase with 8M HCl, and measured by alpha counting (auth)
11 citations