Behavior of I131 Following its Inhalation as a Vapor and as a Particle

Willard, D.H.; Bair, W.J.

doi:10.3109/00016926109175144

Cited by 15 publications

(11 citation statements)

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“…Instead, it is assigned to Type F. However, the data are used as the basis for the default rapid dissolution rate for iodine. Hence, specific parameter values would be the same as default Type F iodine parameter values. (c) Silver iodide (AgI) (192) Following inhalation of 131 I-labelled silver iodide by mice and sheep (Bair, 1961; Willard and Bair, 1961), 131 I was absorbed rapidly from the lungs, even though silver iodide was studied because it is one of the most insoluble iodine compounds in water. Lung retention of 110m Ag following inhalation of 110m Ag-labelled silver iodide by dogs and rats (Morrow et al., 1968) is consistent with assignment to Type M. However, Morrow et al.…”

Section: Iodine (Z = 53)mentioning

confidence: 99%

ICRP Publication 137: Occupational Intakes of Radionuclides: Part 3

Paquet¹,

Bailey²,

Leggett³

et al. 2017

Ann ICRP

236

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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: Iodine (Z = 53)mentioning

confidence: 99%

ICRP Publication 137: Occupational Intakes of Radionuclides: Part 3

Paquet¹,

Bailey²,

Leggett³

et al. 2017

Ann ICRP

236

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“…Animal experiments have shown that with simple ionic compounds (chloride and sulphate) most of the strontium is rapidly cleared, consistent with assignment to TypeF (Bair, 1961;Boecker et al, 1967;Cuddihy and Ozog, 1973;Namenyi et al, 1986).…”

Section: Absorption Typesmentioning

confidence: 63%

“…The absorption of iodide from the gastrointestinal tract of humans is virtually complete with reported values of 0.9 and greater (Riggs, 1952;Willard and Bair, 1961;Wayne et al, 1964;Underwood, 1971). Keating and Albert (1949) reported a rate of absorption of about 5% min-' in fasted individuals, with complete absorption within 2 hours.…”

Section: Iodine (I)mentioning

confidence: 87%

“…Animal investigations using ruthenium citrate and dioxide, indicate that these compounds also exhibit TypeM behavior (Bair, et al, 1961;Boecker and Harris, 1969;Snipes, 1979). However, data from other animal experiments indicate Type M behavior for oxalate, with Type S for dioxide (Newton, et ai., 1976;Newton and Latven, 1971).…”

Section: Particulate Aerosolsmentioning

confidence: 99%

“…The TGLD (1966) assigned halides (including iodides) of elements in Periodic (Willard and Bair, 1961;Bair et al, 1963).…”

Section: Iodinementioning

confidence: 99%

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Probabilistic accident consequence uncertainty analysis -- Uncertainty assessment for internal dosimetry. Volume 2: Appendices

Goossens¹,

Kraan²,

Cooke

et al. 1998

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LEGALNOTICENeither the European Commission nor any person acting on behalf of the Commission is responsible for the use that might be made of the information in this volume. NUREGlCR-6571 ii DISCLAIMERPortions of this document may be illegible in electronic image products. Images are produced from the best available original document. AbstractThe development of two new probabilistic accident consequence codes, MACCS and COSYMA, was completed in 1990.These codes estimate the risk presented by nuclear installations based on postulated frequencies and magnitudes of potential accidents. In 1991, the US Nuclear Regulatory Commission (NRC) and the European Commission (EC) began a joint uncertainty analysis of the two codes. The ultimate objective was to develop credible and traceable uncertainty distributions for the input variables of the codes.The study was formulated jointly and was limited to the current code models and to physical quantities that could be measured in experiments. An elicitation procedure was devised from previous US and EC studies with refinements based on recent experience. Elicitation questions were developed, tested, and clarified. Internationally recognized experts were selected using a common set of criteria. Probability training exercises were conducted to establish ground rules and set the initial and boundary conditions. Experts developed their distributions independently.Aft& the first feasibility study on atmospheric dispersion and deposition parameters, a second expert judgment exercise was carried out on food chain and external dose (calculation) parameters. A third expert judgment exercise has been carried out on early and late health effects and internal dosimetry parameters. The goal again was to develop a library of uncertainty distributions for the selected consequence parameters. Nine experts from five countries were selected for an expert panel on internal dosimetry. Their results were processed with an equal-weighting aggregation method, and the aggregated distributions will be used to determine distributions on the code input parameters of the dose per unit intake (DUPI) models used in COSYMA and for MACCS. PrefaceThis volume is the second of a two-volume document that summarizes a joint project conducted by the US Nuclear Regulatory Commission and the European Commission to assess uncertainties in the MACCS and COSYMA probabilistic accident consequence codes. These codes were developed primarily for estimating the risks presented by nuclear reactors based on postulated frequencies and magnitudes of potential accidents. This document reports on an ongoing project to assess uncertainty in the MACCS and COSYMA calculations for the offsite consequences of radionuclide releases by hypothetical nuclear power plant accidents. A panel of nine experts was formed to compile credible and traceable uncertainty distributions for internal dosimetry input variables that affect calculations of offsite consequences. The expert judgment elicitation procedure and its outcomes are described in...

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1980

Ann ICRP

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Behavior of I131 Following its Inhalation as a Vapor and as a Particle

Cited by 15 publications

References 0 publications

ICRP Publication 137: Occupational Intakes of Radionuclides: Part 3

ICRP Publication 137: Occupational Intakes of Radionuclides: Part 3

Probabilistic accident consequence uncertainty analysis -- Uncertainty assessment for internal dosimetry. Volume 2: Appendices

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