Development and assessment of a new radioactive decay database used for dosimetry calculation

Endo, Akira; Yamaguchi, Y.; Eckerman, K.F.

doi:10.1093/oxfordjournals.rpd.a006304

Cited by 19 publications

(13 citation statements)

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“… (41) A fundamental requirement for dose calculations is reliable information on half-life, modes of decay, and the energies and yields of the various radiations emitted by radionuclides and their progeny (Eckerman et al., 1994; Endo et al., 2003, 2005). The calculations in this report use the nuclear decay data provided in Publication 107 (ICRP, 2008).…”

Section: Introductionmentioning

confidence: 99%

ICRP Publication 130: Occupational Intakes of Radionuclides: Part 1

Paquet¹,

et al. 2015

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This report is the first in a series of reports replacing Publications 30 and 68 to provide revised dose coefficients for occupational intakes of radionuclides by inhalation and ingestion. The revised dose coefficients have been calculated using the Human Alimentary Tract Model (Publication 100) and a revision of the Human Respiratory Tract Model (Publication 66) that takes account of more recent data. In addition, information is provided on absorption into blood following inhalation and ingestion of different chemical forms of elements and their radioisotopes. In selected cases, it is judged that the data are sufficient to make material-specific recommendations. Revisions have been made to many of the models that describe the systemic biokinetics of radionuclides absorbed into blood, making them more physiologically realistic representations of uptake and retention in organs and tissues, and excretion. The reports in this series provide data for the interpretation of bioassay measurements as well as dose coefficients, replacing Publications 54 and 78. In assessing bioassay data such as measurements of whole-body or organ content, or urinary excretion, assumptions have to be made about the exposure scenario, including the pattern and mode of radionuclide intake, physical and chemical characteristics of the material involved, and the elapsed time between the exposure(s) and measurement. This report provides some guidance on monitoring programmes and data interpretation.

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Section: Introductionmentioning

confidence: 99%

ICRP Publication 130: Occupational Intakes of Radionuclides: Part 1

Paquet¹,

et al. 2015

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“…y Ni and e Ni were taken from the nuclear database DECDC (Nuclear Decay Data Files for Dosimetry Calculation) [19] which comply with the data of ICRP Publication 107 [20].…”

Section: Composition Of Conversion Coefficientsmentioning

confidence: 99%

“…First, ambient dose equivalent rates at 1 m height above ground were calculated for exponential sources at various relaxation depths in ground emitting monoenergetic gamma rays. Following, conversion coefficients for radionuclides were composed using recent nuclear data [19] which were adopted by the ICRP [20]. Many radionuclides and a wide range of relaxation depths were considered to cover diverse conditions.…”

Section: Introductionmentioning

confidence: 99%

Ambient dose equivalent conversion coefficients for radionuclides exponentially distributed in the ground

Saitô

Petoussi-Henss

2014

Journal of Nuclear Science and Technology

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Conversion coefficients of radionuclide deposition density to the ambient dose equivalent rate at 1 m height above ground were calculated for exponentially distributed sources in the ground. First, Monte Carlo transport simulations assuming exponential distributions in the ground were performed to obtain ambient dose equivalent for mono-energetic gamma-ray sources having different relaxation depths; next, on the basis of the simulated data, conversion coefficients for radionuclides were composed considering recent nuclear decay data. The ambient dose equivalent rates were then compared to the effective dose rates for reference adults and a new-born baby as well as to air kerma rates quoted from previous studies. It was confirmed that the ambient dose equivalent sufficiently overestimates effective doses, independently of age, for sources exponentially distributed in the ground. Furthermore, the air kerma was found to also overestimate the effective doses for all ages in the same conditions. In order to verify the computed conversion coefficients, the ratio of ambient dose equivalent to air kerma obtained by simulation was compared to the ratios measured at hundreds of locations in Japan which have been contaminated with radioactive cesium after the accident at the nuclear power plant in Fukushima Prefecture, Japan, in 2011; a good agreement was observed.

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“…where f(target source) is the energy absorbed fraction from a source organ to a target organ, and m is the mass of the target organ. Appropriate specific absorbed fraction values, combined with information about radioactive decay and biokinetics for radiopharmaceuticals (9,10) , are essential in the estimation of dose to an organ/structure for a nuclear medicine procedure.…”

Section: Introductionmentioning

confidence: 99%

Specific absorbed fractions for internal electron emitters derived for a set of anatomically realistic reference pregnant female models

Guo

Shi

2009

Radiation Protection Dosimetry

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The specific absorbed fraction (Phi), defined by the Medical Internal Radiation Dose Committee, is generally applied to evaluate the average absorbed dose in a target organ as a result of radioactive materials deposited in a source organ. This paper reports a new set of Phi values for internal electron emitters ranging from 10 keV to 4 MeV from various internal organs of the mother to the fetus based on three newly developed pregnant female tomographic models, called RPI-P3, RPI-P6 and RPI-P9. The results show a linear log relationship between Phi values and electron energy. The linear log coefficients have been derived and reported. The relationship between Phi values and mean distances between source organs and the fetus were also determined to allow for individual dosimetry. Since the RPI-P models have finer details of human anatomy and more realistic organ volumes and geometries, which follow the latest ICRP reference values, the newly derived Phi values could be used as reference values in determination of the dose to the fetus from internal electron emitters.

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Development and assessment of a new radioactive decay database used for dosimetry calculation

Cited by 19 publications

References 0 publications

ICRP Publication 130: Occupational Intakes of Radionuclides: Part 1

ICRP Publication 130: Occupational Intakes of Radionuclides: Part 1

Ambient dose equivalent conversion coefficients for radionuclides exponentially distributed in the ground

Specific absorbed fractions for internal electron emitters derived for a set of anatomically realistic reference pregnant female models

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