ICRP Publication 119: Compendium of Dose Coefficients Based on ICRP Publication 60

2013 ◽  
Vol 42 (4) ◽  
pp. 1-130 ◽  
Author(s):  
K. Eckerman ◽  
J. Harrison ◽  
H-G. Menzel ◽  
C.H. Clement
Keyword(s):  
Dose Coefficients ◽  
Icrp Publication

Basis for the ICRP’s updated biokinetic model for systemic astatnie

2022 ◽  
Author(s):  
Richard Wayne Leggett ◽  
Caleigh Samuels
Keyword(s):  
Salivary Glands ◽  
Intravenous Injection ◽  
Half Life ◽  
Particle Therapy ◽  
Radiation Hazard ◽  
Radiation Doses ◽  
Tissue Dose ◽  
Biokinetic Model ◽  
Dose Coefficients ◽  
Icrp Publication

Abstract The ICRP recently updated its biokinetic models for workers in a series of reports called the OIR (Occupational Intakes of Radionuclides) series. A new biokinetic model for astatine, the heaviest member of the halogen family, was adopted in OIR Part 5 (ICRP Publication 151, in press). This paper provides an overview of available biokinetic data for astatine; describes the basis for the ICRP’s updated model for astatine; and tabulates dose coefficients for intravenous injection of each of the two longest lived and most important astatine isotopes, 211At and 210At. Astatine-211 (T1/2 = 7.214 h) is a promising radionuclide for use in targeted α-particle therapy due to several favorable properties including its half-life and the absence of progeny that could deliver significant radiation doses outside the region of α-particle therapy. Astatine-210 (T1/2 = 8.1 h) is an impurity generated in the production of 211At in a cyclotron and represents a potential radiation hazard via its long-lived progeny 210Po (T1/2 = 138 d). Tissue dose coefficients for injected 210At and 211At based on the updated model are shown to differ considerably from values based on the ICRP’s previous model for astatine, particularly for the thyroid, stomach wall, salivary glands, lungs, spleen, and kidneys.

scholarly journals ICRP Publication 144: Dose Coefficients for External Exposures to Environmental Sources

2020 ◽  
Vol 49 (2) ◽  
pp. 11-145
Author(s):  
N. Petoussi-Henss ◽  
D. Satoh ◽  
A. Endo ◽  
K.F. Eckerman ◽  
W.E. Bolch ◽  
...  
Keyword(s):  
Dose Coefficients ◽  
External Exposures ◽  
Icrp Publication

scholarly journals COEFFICIENTS FOR ESTIMATING PRENATAL DOSE IN PREGNANT WORKERS FROM ACUTE INTAKES

2020 ◽  
Vol 191 (1) ◽  
pp. 39-120
Author(s):  
Scott O Schwahn ◽  
Caleigh E Samuels ◽  
Richard W Leggett
Keyword(s):  
Effective Dose ◽  
Half Life ◽  
International Commission ◽  
Radiological Protection ◽  
Multiple Forms ◽  
Ingestion Dose ◽  
Scaling Factors ◽  
Dose Coefficients ◽  
The Many ◽  
Icrp Publication

Abstract Inhalation and ingestion dose coefficients for the embryo and fetus from intakes of radionuclides by the mother are provided in the International Commission on Radiological Protection (ICRP) Publication 88 for intake of each of 74 radionuclides. To address the many other possible radionuclides to which workers may be exposed, effective dose coefficients were developed for the embryo/fetus for all additional radionuclides addressed in ICRP Publication 107 with half-life of 10 min or more. The general approach was to use the estimated dose to the mother’s uterus during pregnancy as a scalable proxy for the dose to the embryo/fetus. The set of scaling factors used in the study was derived from analyses of the relationships of the dose to the mother’s uterus and the effective dose to the embryo/fetus for the ~400 cases (considering two intake modes and multiple forms of many of the radionuclides) addressed in Publication 88.

ICRP Task Group 95: internal dose coefficients

2018 ◽  
Vol 47 (3-4) ◽  
pp. 63-74 ◽  
Author(s):  
F. Paquet ◽  
J. Harrison
Keyword(s):  
Dose Assessment ◽  
Radiological Protection ◽  
Monitoring Methods ◽  
The Public ◽  
The Past ◽  
Workplace Monitoring ◽  
Dose Coefficients ◽  
Bioassay Data ◽  
General Aspects ◽  
Icrp Publication

Internal doses are calculated using biokinetic and dosimetric models. These models describe the behaviour of the radionuclides after ingestion, inhalation, and absorption to the blood, and the absorption of the energy resulting from their nuclear transformations. The International Commission on Radiological Protection (ICRP) develops such models and applies them to provide dose coefficients and bioassay functions for the calculation of equivalent or effective dose from knowledge of intakes and/or measurements of activity in bioassay samples. Over the past few years, ICRP has devoted a considerable amount of effort to the revision and improvement of models to make them more physiologically realistic representations of uptake and retention in organs and tissues, and of excretion. Provision of new biokinetic models, dose coefficients, monitoring methods, and bioassay data is the responsibility of Committee 2 and its task groups. Three publications in a series of documents replacing the ICRP Publication 30 series and ICRP Publications 54, 68, and 78 have been issued [Occupational Intakes of Radionuclides (OIR) Parts 1–3]. OIR Part 1 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 Parts 2–5 provide data on individual elements and their radioisotopes. Work is also in progress on revision of dose coefficients for radionuclide intakes by members of the public.

Doses from radiation exposure

2012 ◽  
Vol 41 (3-4) ◽  
pp. 12-23 ◽  
Author(s):  
H-G. Menzel ◽  
J.D. Harrison
Keyword(s):  
Radiation Exposure ◽  
Effective Dose ◽  
Internal Exposure ◽  
Physiological Data ◽  
Practical Implementation ◽  
Imaging Data ◽  
Task Groups ◽  
Dose Coefficients ◽  
External Exposures ◽  
Icrp Publication

Practical implementation of the International Commission on Radiological Protection's (ICRP) system of protection requires the availability of appropriate methods and data. The work of Committee 2 is concerned with the development of reference data and methods for the assessment of internal and external radiation exposure of workers and members of the public. This involves the development of reference biokinetic and dosimetric models, reference anatomical models of the human body, and reference anatomical and physiological data. Following ICRP's 2007 Recommendations, Committee 2 has focused on the provision of new reference dose coefficients for external and internal exposure. As well as specifying changes to the radiation and tissue weighting factors used in the calculation of protection quantities, the 2007 Recommendations introduced the use of reference anatomical phantoms based on medical imaging data, requiring explicit sex averaging of male and female organ-equivalent doses in the calculation of effective dose. In preparation for the calculation of new dose coefficients, Committee 2 and its task groups have provided updated nuclear decay data (ICRP Publication 107) and adult reference computational phantoms (ICRP Publication 110). New dose coefficients for external exposures of workers are complete (ICRP Publication 116), and work is in progress on a series of reports on internal dose coefficients to workers from inhaled and ingested radionuclides. Reference phantoms for children will also be provided and used in the calculation of dose coefficients for public exposures. Committee 2 also has task groups on exposures to radiation in space and on the use of effective dose.

scholarly journals ICRP recommendations on radon

2020 ◽  
Vol 49 (1_suppl) ◽  
pp. 68-76 ◽  
Author(s):  
J.D. Harrison ◽  
J.W. Marsh
Keyword(s):  
Occupational Exposure ◽  
Reference Level ◽  
Radiological Protection ◽  
Radiation Doses ◽  
Site Specific ◽  
Detailed Consideration ◽  
Equilibrium Factor ◽  
Dose Coefficient ◽  
Dose Coefficients ◽  
Icrp Publication

The International Commission on Radiological Protection (ICRP) publishes guidance on protection from radon in homes and workplaces, and dose coefficients for use in assessments of exposure for protection purposes. ICRP Publication 126 recommends an upper reference level for exposures in homes and workplaces of 300 Bq m−3. In general, protection can be optimised using measurements of air concentrations directly, without considering radiation doses. However, dose estimates are required for workers when radon is considered as an occupational exposure (e.g. in mines), and for higher exposures in other workplaces (e.g. offices) when the reference level is exceeded persistently. ICRP Publication 137 recommends a dose coefficient of 3 mSv per mJ h m−3 (approximately 10 mSv per working level month) for most circumstances of exposure in workplaces, equivalent to 6.7 nSv per Bq h m−3 using an equilibrium factor of 0.4. Using this dose coefficient, annual exposure of workers to 300 Bq m−3 corresponds to 4 mSv. For comparison, using the same coefficient for exposures in homes, 300 Bq m−3 corresponds to 14 mSv. If circumstances of occupational exposure warrant more detailed consideration and reliable alternative data are available, site-specific doses can be assessed using methodology provided in ICRP Publication 137.

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