Physico-chemical characteristics of uranium compounds: A review

Davesne, Estelle; Blanchardon, E.

doi:10.3109/09553002.2014.886796

Cited by 10 publications

(18 citation statements)

References 80 publications

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“…(2002) compiled absorption parameter values derived from the results of a large number of in-vivo and in-vitro studies carried out on materials from French and UK nuclear fuel fabrication facilities. More recently, Davesne and Blanchardon (2014) compiled published values of HRTM absorption parameters and aerosol size distributions for uranium compounds in different workplaces. (828) As described below, specific parameter values based on in-vivo data could be derived for several materials. Four of them – uranium nitrate, peroxide, trioxide, and ammonium diuranate – are relatively soluble, and their behaviour is intermediate between that represented by Type F and Type M defaults.…”

Section: Uranium (Z = 92)mentioning

confidence: 99%

Section: Uranium (Z = 92)mentioning

confidence: 99%

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ICRP Publication 137: Occupational Intakes of Radionuclides: Part 3

Paquet¹,

Bailey²,

Leggett³

et al. 2017

Ann ICRP

234

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The 2007 Recommendations of the International Commission on Radiological Protection (ICRP, 2007) introduced changes that affect the calculation of effective dose, and implied a revision of the dose coefficients for internal exposure, published previously in the Publication 30 series (ICRP, 1979, 1980, 1981, 1988) and Publication 68 (ICRP, 1994). In addition, new data are now available that support an update of the radionuclide-specific information given in Publications 54 and 78 (ICRP, 1988a, 1997b) for the design of monitoring programmes and retrospective assessment of occupational internal doses. Provision of new biokinetic models, dose coefficients, monitoring methods, and bioassay data was performed by Committee 2, Task Group 21 on Internal Dosimetry, and Task Group 4 on Dose Calculations. A new series, the Occupational Intakes of Radionuclides (OIR) series, will replace the Publication 30 series and Publications 54, 68, and 78. OIR Part 1 has been issued (ICRP, 2015), and describes the assessment of internal occupational exposure to radionuclides, biokinetic and dosimetric models, methods of individual and workplace monitoring, and general aspects of retrospective dose assessment. OIR Part 2 (ICRP, 2016), this current publication and upcoming publications in the OIR series (Parts 4 and 5) provide data on individual elements and their radioisotopes, including information on chemical forms encountered in the workplace; a list of principal radioisotopes and their physical half-lives and decay modes; the parameter values of the reference biokinetic model; and data on monitoring techniques for the radioisotopes encountered most commonly in workplaces. Reviews of data on inhalation, ingestion, and systemic biokinetics are also provided for most of the elements. Dosimetric data provided in the printed publications of the OIR series include tables of committed effective dose per intake (Sv Bq−1 intake) for inhalation and ingestion, tables of committed effective dose per content (Sv Bq−1 measurement) for inhalation, and graphs of retention and excretion data per Bq intake for inhalation. These data are provided for all absorption types and for the most common isotope(s) of each element. The electronic annex that accompanies the OIR series of publications contains a comprehensive set of committed effective and equivalent dose coefficients, committed effective dose per content functions, and reference bioassay functions. Data are provided for inhalation, ingestion, and direct input to blood. This third publication in the series provides the above data for the following elements: ruthenium (Ru), antimony (Sb), tellurium (Te), iodine (I), caesium (Cs), barium (Ba), iridium (Ir), lead (Pb), bismuth (Bi), polonium (Po), radon (Rn), radium (Ra), thorium (Th), and uranium (U).

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Section: Uranium (Z = 92)mentioning

confidence: 99%

Section: Uranium (Z = 92)mentioning

confidence: 99%

ICRP Publication 137: Occupational Intakes of Radionuclides: Part 3

Paquet¹,

Bailey²,

Leggett³

et al. 2017

Ann ICRP

234

View full text Add to dashboard Cite

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“…The derived AMADs in the present work are generally considerably higher than previously published data (Davesne and Blanchardon 2014). This might be due to aerosol characteristics associated with the particular production method.…”

Section: Samplingcontrasting

confidence: 74%

“…Thind reported an AMAD of 6.1 mm and GSD of 2.1 (Thind 1986). A more recent review paper stated an average AMAD of 6.2 mm with a GSD of 2.3 (Davesne and Blanchardon 2014). An earlier review paper stated that results below 1 mm were inconsistent, suggesting a bimodal size distribution (Dorrian and Bailey 1995).…”

Section: Introductionmentioning

confidence: 99%

“…An earlier review paper stated that results below 1 mm were inconsistent, suggesting a bimodal size distribution (Dorrian and Bailey 1995). Available data are based on static sampling and might not be representative of the breathing zone of operators (Davesne and Blanchardon 2014). To the best of our knowledge, AMADs determined from cascade impactor sampling in the breathing zone of workers in nuclear fuel fabrication have not been published by open sources.…”

Section: Introductionmentioning

confidence: 99%

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Uranium Aerosol Activity Size Distributions at a Nuclear Fuel Fabrication Plant

2020

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Inhalation of uranium aerosols is a concern in nuclear fuel fabrication. Determination of committed effective doses and lung equivalent doses following inhalation intake requires knowledge about aerosol characteristics; e.g., the activity median aerodynamic diameter (AMAD). Cascade impactor sampling of uranium aerosols in the breathing zone of nuclear operators was carried out at a nuclear fuel fabrication plant producing uranium dioxide via ammonium uranyl carbonate. Complementary static sampling was carried out at key process steps. Uranium on impaction substrates was measured using gross alpha counting and alpha spectrometry. Activity size distributions were evaluated for both unimodal and bimodal distributions. When a unimodal distribution was assumed, the average AMAD in the operator breathing zone at the workshops was 12.9–19.3 μm, which is larger than found in previous studies. Certain sampling occasions showed variable isotope ratios ( 234 U/ 238 U) at different impactor stages, indicating more than one population of particles; i.e., a multimodal activity size distribution. When a bimodal distribution (coarse and fine fraction) was assumed, 75–88% of the activity was associated with an AMAD of 15.2–18.9 μm (coarse fraction). Quantification of the AMAD of the fine fraction was associated with large uncertainties. Values of 1.7–7.1 μm were obtained. Static sampling at key process steps in the workshops showed AMADs of 4.9–17.2 μm, generally lower than obtained by breathing zone sampling, when a unimodal distribution was assumed. When a bimodal distribution was assumed, a smaller fraction of the activity was associated with the coarse fraction compared to breathing zone sampling. This might be due to impactor positioning during sampling and sedimentation of large particles. The average committed effective dose coefficient for breathing zone sampling and a bimodal distribution was 1.6–2.6 μSv Bq −1 for 234 U when Type M/S absorption parameters were assumed (5.0 μSv Bq −1 for an AMAD of 5 μm). The corresponding lung equivalent dose coefficient was 3.6–10.7 μSv Bq −1 (29.9 μSv Bq −1 for an AMAD of 5 μm). The predicted urinary excretion level 100 d after inhalation intake was found to be 13-34% of that corresponding to an AMAD of 5 μm. Uranium aerosols generated at a nuclear fuel fabrication plant using ammonium uranyl carbonate route of conversion were associated with larger AMADs compared to previous work, especially when sampling of aerosols was carried out in the operator breathing zone. A bimodal activity size distribution can be used in calculations of committed effective doses and lung equivalent doses, but parameters associated with the fine fraction must be interpreted with care due to large uncertainties.

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