The distribution and excretion of trivalent antimony in the rat following inhalation

Djurić, Dušan; Thomas, Robert G.; Lie, R.

doi:10.1007/bf00391679

Cited by 20 publications

(5 citation statements)

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“… (a) Antimony chloride (84) Djurić et al. (1962) followed the biokinetic of 124 Sb after inhalation of antimony chloride by rats for 140 d. From the results, absorption parameter values calculated here (i.e.…”

Section: Antimony (Z = 51)mentioning

confidence: 99%

“…The liver, kidneys, and muscle each contained 0.1% or less of the injected amount. Urinary excretion accounted for 96.5% of total excretion over the 4-day period. (122) Djuric et al. (1962) studied the distribution and excretion of 124 Sb in rats after inhalation of an aerosol of 124 SbCl 3 .…”

Section: Antimony (Z = 51)mentioning

confidence: 99%

“…(122) Djuric et al. (1962) studied the distribution and excretion of 124 Sb in rats after inhalation of an aerosol of 124 SbCl 3 .…”

Section: Antimony (Z = 51)mentioning

confidence: 99%

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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: Antimony (Z = 51)mentioning

confidence: 99%

Section: Antimony (Z = 51)mentioning

confidence: 99%

See 1 more Smart Citation

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

“…After oral ingestion, less than 10 % of antimony tartrate and 1 % of all other forms of antimony are absorbed [17]. Valence states determine the distribution of antimony in blood and [129] g Because these substances exist in the atmosphere in the particulate state, the concentration is expressed as mg/m 3 tissues [15,18]. After inhalation, the trivalent and pentavalent forms concentrate in the erythrocytes and plasma.…”

Section: Biochemistry and Clinical Pharmacologymentioning

confidence: 99%

Antimony and Nickel

Sztajnkrycer¹

2016

Critical Care Toxicology

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“…Radiolabeled antimony tracer studies demonstrated that both rats and monkeys excreted a large fraction of the administered dose in the urine within 2 h of administration (Waitz et al 1965). Djurić et al (1962) studied the kinetics of trivalent antimony in the rat, and found slightly greater fecal elimination in comparison with urine, and a multiexponential elimination curve to be observed. A biological half-life of 16 days was reported for antimony by Felicetti et al (1974) in hamsters following inhalation exposure to both valence states.…”

Section: Uptake Absorption Transport and Distribution Metabolism Amentioning

confidence: 99%

Antimony

Rish¹

2004

Elements and Their Compounds in the Environment

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The distribution and excretion of trivalent antimony in the rat following inhalation

Cited by 20 publications

References 12 publications

ICRP Publication 137: Occupational Intakes of Radionuclides: Part 3

ICRP Publication 137: Occupational Intakes of Radionuclides: Part 3

Antimony and Nickel

Antimony

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