A Study of Uranium Lung Clearance at a Uranium Processing Plant

Barber, J.M.; Forrest, Robert D.

doi:10.1097/00004032-199505000-00005

Cited by 6 publications

(2 citation statements)

References 0 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…These parameter values are adopted here for uranium aluminide. (j) Uranium octoxide (U 3 O 8 ) (849) Uranium octoxide can be present at various stages in the uranium fuel cycle. Human data from accidental intake of U 3 O 8 (Saxby et al., 1964; West et al., 1979; Eidson, 1990); and from monitoring data for workers in processing facilities (Chalabreysse et al., 1989; Barber and Forrest, 1995); animal studies using rats, dogs, and monkeys (Stradling et al., 1989; Métivier et al., 1992); and in-vitro studies (Eidson, 1994; Ansoborlo et al., 1998a; Chazel et al., 1998) have shown that the biokinetic behaviour of this compound depends on the particular process of manufacture. A study of the influence of specific surface area (Chazel et al., 1998) demonstrated the importance of this parameter on dissolution characteristics.…”

Section: Uranium (Z = 92)mentioning

confidence: 99%

ICRP Publication 137: Occupational Intakes of Radionuclides: Part 3

Paquet¹,

Bailey²,

Leggett³

et al. 2017

Ann ICRP

236

View full text Add to dashboard Cite

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).

show abstract

Section: Uranium (Z = 92)mentioning

confidence: 99%

ICRP Publication 137: Occupational Intakes of Radionuclides: Part 3

Paquet¹,

Bailey²,

Leggett³

et al. 2017

Ann ICRP

236

View full text Add to dashboard Cite

show abstract

“…Table 3.2. Leach et al 1973;Cook and Holt 1974;Pomroy and Noel 1981;Schieferdecker et al 1985;Price 1989;Stradling et al 1989b;Métivier et al 1992;Eidson 1994;Chazel et al 2000b;Ansoborlo et al 2002;Stradling et al 2002 Uranium West et al 1979;Eidson and Mewhinney 1980;Chalabreysse et al 1989;Stradling et al 1989aStradling et al , 2002Eidson 1990Eidson , 1994Métivier et al 1992;Barber and Forrest 1995;Ansoborlo et al 1998bAnsoborlo et al , 2002Chazel et al 1998 Uranium Stradling et al 1985Stradling et al , 2002Chalabreysse et al 1989;André et al 1989;Ansoborlo et al 1990Ansoborlo et al , 2002Eidson 1994;Chazel et al 2000a Uranium Galibin and Parfenov 1971;Cook and Holt 1974;Boback 1975;Eidson and Mewhinney 1980;Damon et al 1984;Stradling et al 1987Stradling et al , 2002Eidson 1994;Ansoborlo et al 2002 In vitro studies indicate dissolution rate varies with mixture of materials and preparation process. Differences found in dissolution rates of low-fired yellowcake (dried at less than 400° C) and high-fired (calcined) yellowcake (dried at 4...…”

Section: Application Of the Hrtm To Various Forms Of Uraniummentioning

confidence: 99%

Controlling intake of uranium in the workplace: Applications of biokinetic modeling and occupational monitoring data

Leggett¹,

Eckerman²,

McGinn³

et al. 2012

View full text Add to dashboard Cite

This report provides methods to interpret and apply occupational uranium monitoring data. The methods are based on current international radiation protection guidance, current information on the chemical toxicity of uranium, and best available biokinetic models for uranium. Emphasis is on air monitoring data and three types of bioassay data: the concentration of uranium in urine; the concentration of uranium in feces; and the externally measured content of uranium in the chest. Primary Reference guidance levels for prevention of chemical effects and limitation of radiation effects are selected based on a review of current scientific data and regulatory principles for setting standards. Generic investigation levels and immediate action levels are then defined in terms of these primary guidance levels. The generic investigation and immediate actions levels are stated in terms of radiation dose and concentration of uranium in the kidneys. These are not directly measurable quantities, but models can be used to relate the generic levels to the concentration of uranium in air, urine, or feces, or the total uranium activity in the chest. Default investigation and immediate action levels for uranium in air, urine, feces, and chest are recommended for situations in which there is little information on the form of uranium taken into the body. Methods are prescribed also for deriving case-specific investigation and immediate action levels for uranium in air, urine, feces, and chest when there is sufficient information on the form of uranium to narrow the range of predictions of accumulation of uranium in the main target organs for uranium: kidneys for chemical effects and lungs for radiological effects. In addition, methods for using the information herein for alternative guidance levels, different from the ones selected for this report, are described. v FOREWORDThis report provides a detailed description of uranium biokinetics and bioassays applicable to evaluation of health risks from potential intakes in an occupational setting. The report addresses both the radiotoxicity and chemical (renal) toxicity of uranium. For reference occupational exposure scenarios, predictions of the time-dependent concentration of uranium in tissues and bioassay are based on biokinetic models currently recommended by the International Commission on Radiological Protection (ICRP). The ICRP's models and default assumptions for uranium were based primarily on data for human subjects exposed to uranium in controlled studies or in occupational or environmental settings. In addition, the ICRP considered an extensive database for uranium in laboratory animals. Sensitivity studies examine the robustness of these models and assumptions to ensure that radiation doses and accumulation of uranium in the kidneys are not underestimated. For example, analyses indicate that a default 5 µm activity median aerodynamic diameter particle size can lead to an underestimation of radiation dose as well as the concentration of uranium in the kidneys if inhal...

show abstract

Age-dependent doses to members of the public from intake of radionuclides: Part 4 Inhalation dose coefficients

Icrp¹

1995

Ann ICRP

410

View full text Add to dashboard Cite

A Study of Uranium Lung Clearance at a Uranium Processing Plant

Cited by 6 publications

References 0 publications

ICRP Publication 137: Occupational Intakes of Radionuclides: Part 3

ICRP Publication 137: Occupational Intakes of Radionuclides: Part 3

Controlling intake of uranium in the workplace: Applications of biokinetic modeling and occupational monitoring data

Age-dependent doses to members of the public from intake of radionuclides: Part 4 Inhalation dose coefficients

Contact Info

Product

Resources

About