Proton nuclear activation in stable tracer technique for ruthenium metabolism studies

Cantone, M.C.; Bartolo, D. de; Gambarini, G.; Giussani, A.; Ottolenghi, A.; Pirola, L.; Hansen, Ch.; Roth, P.; Werner, E.

doi:10.1016/0168-9002(94)91694-2

Cited by 14 publications

(4 citation statements)

References 8 publications

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“…(1971) estimated the absorption of ruthenium in cats given nitrosyl ruthenium compounds as between 0.1 and 0.15. Cantone et al. (1994) used stable isotopes to estimate absorption in a rabbit as 0.06. (61) In Publication 30 (ICRP, 1980), an absorption value of 0.05 was recommended for all chemical forms of ruthenium.…”

Section: Ruthenium (Z=44)mentioning

confidence: 99%

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ICRP Publication 137: Occupational Intakes of Radionuclides: Part 3

Paquet¹,

Bailey²,

Leggett³

et al. 2017

Ann ICRP

206

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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: Ruthenium (Z=44)mentioning

confidence: 99%

Section: Ruthenium (Z=44)mentioning

confidence: 99%

ICRP Publication 137: Occupational Intakes of Radionuclides: Part 3

Paquet¹,

Bailey²,

Leggett³

et al. 2017

Ann ICRP

206

View full text Add to dashboard Cite

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“…Up to 39 samples can be activated under the same experimental conditions, as the disc rotates at a speed of approximately 70 r.p.m, placing one sample after the other in front of the beam line. On the basis of the optimization work performed previously [20], the nuclear reaction chosen for the determination of the ruthenium tracer is 101 Ru(p, n) 101m Rh. The reaction product has a half-life of 4.34 days, and can be selectively determined in the activated sample through the measurement of its gamma emission at 306.9 keV.…”

Section: Sample Analysismentioning

confidence: 99%

“…A methodology for conducting Ru biokinetic studies based on stable tracer administration and activation analysis with charged particles was presented in a previous paper [20] and applied to animal studies [21]. No significant mass effects on the Ru kinetics in plasma were observed in those studies, where radioactive and/or stable tracers were administered in amounts ranging from about 30 pg Ru to 90 µg Ru per kg body weight.…”

Section: Introductionmentioning

confidence: 99%

Kinetics of systemic ruthenium in human blood using a stable tracer

et al. 2001

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The biokinetics of ruthenium after oral and intravenous administration has been investigated in two human subjects using the stable isotope 101Ru as a tracer. Tracer concentrations in blood plasma have been determined using activation analysis with protons. The results presented here prove that the stable tracer technique is a valuable tool for obtaining relevant information about the biokinetics of ruthenium in humans. From these pilot studies, it may be argued that the clearance of systemic ruthenium from plasma is significantly slower than the predictions of the biokinetic model currently recommended by the International Commission on Radiological Protection (ICRP). The experimental data for the orally administered tracer, which reflect the gastrointestinal absorption process, differ from the curve derived from the ICRP model, suggesting that the uptake into the systemic circulation may be lower than predicted. On the basis of these preliminary data, investigations on a larger number of subjects with improvements in the experimental design are scheduled.

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