Radiochemical Determinations of Uranium, Thorium and Plutonium in Soft Tissues

Singh, Narayani P.; Zimmerman, Carol J.; Lewis, L.; Wrenn, M.E.

doi:10.1524/ract.1984.35.4.219

Cited by 11 publications

(7 citation statements)

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“…Uranium, Th, and Pu were determined in soft tissues by a radiochemical procedure developed by Singh et al ( 1984a). The tissues were first spiked with 232U, 22yTh, and 242Pu tracers and wet-ashed.…”

Section: Radiochemical Determinations Of U Th Und Pumentioning

confidence: 99%

Is the Beagle Dog an Appropriate Experimental Animal for Extrapolating Data to Humans on Organ Distribution Patterns of U, Th, and Pu?

Singh¹,

Wrenn²

1989

Health Physics

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Concentrations and organ distribution patterns of alpha-emitting isotopes of U (238U and 234U), Th (232Th, 230Th, and 228Th), and Pu (239,240Pu) were determined for beagle dogs of our colony. The dogs were exposed to environmental levels of U and Th isotopes through ingestion (food and water) and inhalation to stimulate environmental exposures of the general human population. The organ distribution patterns of these radionuclides in beagles are compared to patterns in humans to determine if it is appropriate to extrapolate organ content data from beagles to humans. The results indicated that approximately 80% of the U and Th accumulated in bone in both species. The organ content percentages of these radionuclides in soft tissues such as liver, kidney, etc. of both species were comparable. The human lung contained higher percentages of U and Th than the beagle lung, perhaps because the longer life span of humans resulted in a longer exposure time. If the U and Th content of dog lung is normalized to an exposure time of 58 y and 63 y, median ages of the U and Th study populations, respectively, the lung content for both species is comparable. The organ content of 239,240Pu in humans and beagles differed slightly. In the beagle, the liver contained more than 60%, and the skeleton contained less than 40% of the Pu body content. In humans, the liver contained approximately 37%, and the skeleton contained approximately 58% of the body content. This difference may have been due to differences in the mode of intake of Pu in each species or to differences in the chemical form of Pu. In general, the results suggest that the beagle may be an appropriate experimental animal from which to extrapolate data to humans with reference to the percentage of U, Th, and Pu found in the organs.

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Section: Radiochemical Determinations Of U Th Und Pumentioning

confidence: 99%

Is the Beagle Dog an Appropriate Experimental Animal for Extrapolating Data to Humans on Organ Distribution Patterns of U, Th, and Pu?

Singh¹,

Wrenn²

1989

Health Physics

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“…Evaluation of a uranium intake resulting from an occupational accident is always complicated by chronic exposure to low-levels of natural uranium due to the ubiquitous presence of uranium in food, water, and atmospheric air. For US residents, published estimates of the daily uranium intake from ingestion range from 1.3 to 4.4 μg d −1 (Welford and Baird 1967, Wrenn et al 1985, Fisenne and Welford 1986, Singh et al 1986, 1990, Fisenne et al 1987). Wrenn et al (1985 estimated a daily rate of 1.75 μg d −1 for dietary U intake by reference man in the eastern part of the United States while the average dietary intake rate of 4.4 μg d −1 was reported by 1994b).…”

Section: Introductionmentioning

confidence: 99%

US Transuranium and Uranium Registries case study on accidental exposure to uranium hexafluoride

et al. 2015

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The United States Transuranium and Uranium Registries' (USTUR) whole-body donor (Case 1031) was exposed to an acute inhalation of uranium hexafluoride (UF6) produced from an explosion at a uranium processing plant 65 years prior to his death. The USTUR measurements of tissue samples collected at the autopsy indicated long-term retention of inhaled slightly enriched uranium material (0.85% (235)U) in the deep lungs and thoracic lymph nodes. In the present study, the authors combined the tissue measurement results with historical bioassay data, and analysed them with International Commission on Radiological Protection (ICRP) respiratory tract models and the ICRP Publication 69 systemic model for uranium using maximum likelihood and Bayesian statistical methods. The purpose of the analysis was to estimate intakes and model parameter values that best describe the data, and evaluate their effect on dose assessment. The maximum likelihood analysis, which used the ICRP Publication 66 human respiratory tract model, resulted in a point estimate of 79 mg of uranium for the occupational intake composed of 86% soluble, type F material and 14% insoluble, type S material. For the Bayesian approach, the authors applied the Markov Chain Monte Carlo method, but this time used the revised human respiratory tract model, which is currently being used by ICRP to calculate new dose coefficients for workers. The Bayesian analysis estimated that the mean uranium intake was 160 mg, and calculated the case-specific lung dissolution parameters with their associated uncertainties. The parameters were consistent with the inhaled uranium material being predominantly soluble with a small but significant insoluble component. The 95% posterior range of the rapid dissolution fraction (the fraction of deposited material that is absorbed to blood rapidly) was 0.12 to 0.91 with a median of 0.37. The remaining fraction was absorbed slowly, with a 95% range of 0.000 22 d(-1) to 0.000 36 d(-1) and a median of 0.000 31 d(-1). The effective dose per unit intake calculated using the dissolution parameters derived from the maximum likelihood and the Bayesian analyses was higher than the current ICRP dose coefficient for type F uranium by a factor of 2 or 7, respectively; the higher value of the latter was due to use of the revised respiratory tract model. The dissolution parameter values obtained here may be more appropriate to use for radiation protection purposes when individuals are exposed to a UF6 mixture that contains an insoluble uranium component.

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“…16−21 However, to the best of our knowledge, works reported on the usage of iron hydroxide coprecipitation for biological sample analysis are very rare. 22 This might be a consequence of the complicated and variable composition of urine matrix which might influence the analytical performance of iron hydroxide coprecipitation.…”

mentioning

confidence: 99%

“…Iron hydroxide coprecipitation is a traditional method of choice for determination of trace levels Np and Pu. Due to its simplicity and cost-effectiveness, iron hydroxide coprecipitation has been extensively used to isolate Np and Pu from environmental samples with different matrix composition including fresh water, seawater, soil, sediment, seaweed, etc. − However, to the best of our knowledge, works reported on the usage of iron hydroxide coprecipitation for biological sample analysis are very rare . This might be a consequence of the complicated and variable composition of urine matrix which might influence the analytical performance of iron hydroxide coprecipitation.…”

mentioning

confidence: 99%

Sequential Injection Approach for Simultaneous Determination of Ultratrace Plutonium and Neptunium in Urine with Accelerator Mass Spectrometry

et al. 2013

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An analytical method was developed for simultaneous determination of ultratrace level plutonium (Pu) and neptunium (Np) using iron hydroxide coprecipitation in combination with automated sequential injection extraction chromatography separation and accelerator mass spectrometry (AMS) measurement. Several experimental parameters affecting the analytical performance were investigated and compared including sample preboiling operation, aging time, amount of coprecipitating reagent, reagent for pH adjustment, sedimentation time, and organic matter decomposition approach. The overall analytical results show that preboiling and aging are important for obtaining high chemical yields for both Pu and Np, which is possibly related to the aggregation and adsorption behavior of organic substances contained in urine. Although the optimal condition for Np and Pu simultaneous determination requires 5-day aging time, an immediate coprecipitation without preboiling and aging could also provide fairly satisfactory chemical yields for both Np and Pu (50-60%) with high sample throughput (4 h/sample). Within the developed method, (242)Pu was exploited as chemical yield tracer for both Pu and Np isotopes. (242)Pu was also used as a spike in the AMS measurement for quantification of (239)Pu and (237)Np concentrations. The results show that, under the optimal experimental condition, the chemical yields of (237)Np and (242)Pu are nearly identical, indicating the high feasibility of (242)Pu as a nonisotopic tracer for (237)Np determination in real urine samples. The analytical method was validated by analysis of a number of urine samples spiked with different levels of (237)Np and (239)Pu. The measured values of (237)Np and (239)Pu by AMS exhibit good agreement (R(2) ≥ 0.955) with the spiked ones confirming the reliability of the proposed method.

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Radiochemical Determinations of Uranium, Thorium and Plutonium in Soft Tissues

Cited by 11 publications

References 0 publications

Is the Beagle Dog an Appropriate Experimental Animal for Extrapolating Data to Humans on Organ Distribution Patterns of U, Th, and Pu?

Is the Beagle Dog an Appropriate Experimental Animal for Extrapolating Data to Humans on Organ Distribution Patterns of U, Th, and Pu?

US Transuranium and Uranium Registries case study on accidental exposure to uranium hexafluoride

Sequential Injection Approach for Simultaneous Determination of Ultratrace Plutonium and Neptunium in Urine with Accelerator Mass Spectrometry

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