Age-dependent Doses to Members of the Public from intake of Radionuclides: Part 5 Compilation of Ingestion and Inhalation Dose Coefficients (ICRP Publication 72)

1996 ◽  
Vol 41 (12) ◽  
pp. 2807-2807 ◽  
Author(s):  
P C Jackson
Keyword(s):  
Inhalation Dose ◽  
The Public ◽  
Age Dependent ◽  
Dose Coefficients ◽  
Icrp Publication

7. Inhalation dose coefficients for members of the public: labelled methane: (Addendum 1 to ICRP Publication 72)

1998 ◽  
Vol 28 (3) ◽  
pp. 123-123
Author(s):  
D. J. Valentin
Keyword(s):  
Inhalation Dose ◽  
The Public ◽  
Task Groups ◽  
Age Dependent ◽  
Dose Coefficients ◽  
Icrp Publication

This is an Addendum to ICRP Publication 72 concerning age-dependent doses to members of the public from intakes of radionuclides. It provides inhalation dose coefficients for labelled methane for members of the public, jointly prepared by two Task Groups of ICRP Committee 2.

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.

Radiation dose to patients from radiopharmaceuticals: (Addendum 2 to ICRP Publication 53) ICRP Publication 80 Approved by the Commission in September 1997

1998 ◽  
Vol 28 (3) ◽  
pp. 1-1 ◽  
Author(s):  
J. Valentin
Keyword(s):  
Carbon Dioxide ◽  
Fatty Acids ◽  
Radiation Dose ◽  
Unit Activity ◽  
The Public ◽  
Absorbed Doses ◽  
Joint Task ◽  
Age Dependent ◽  
Effective Doses ◽  
Icrp Publication

A joint Task Group of ICRP Committees 2 (Doses from Radiation Exposures) and 3 (Protection in Medicine; lead Committee for this report) has prepared a compilation of data on radiation dose to patients from radiopharmaceuticals. The report provides biokinetic models, absorbed doses, and effective doses, using ICRP Publication 60 dosimetry, for 10 new radiopharmaceuticals: [Methyl-11C]thymidine; [2-11C]thymidine; 14C urea (incl. carbon dioxide and bicarbonate); 15O water; 99mTc HIG, Pertechnegas, Technegas, and tetrofosmin; and 111In HIG and octreotide. It also provides recalculated dose data for the 19 most frequently used radiopharmaceuticals from ICRP Publication 53, using ICRP Publication 60 dosimetry, viz. 18F FDG; 51Cr EDTA; 67Ga citrate; 75Se SeHCAT; 99mTc DMSA, DTPA, RBC, IDA, large colloids, WBC, MAA, non-absorbable markers, pertechnetate, and phosphates and phosphonates; 123I Hippuran and MIBG; 131I Hippuran and NP59; and 201Tl thallous ion. Printing errors detected in ICRP Publication 53 are also listed. Furthermore, the report reproduces with minor corrections and updates, and therefore supersedes, the information on 6 radiopharmaceuticals given in Addendum 1 to ICRP Publication 53: 3H neutral fat and fatty acids; 14C neutral fat and fatty acids; 68Ga EDTA; and 99mTc HM-PAO, MAG3, and MIBI. There is an integrated index to all radiopharmaceuticals treated in ICRP publications so far, including a listing of effective doses per unit activity administered to adults. This issue of the Annals of the ICRP also includes an Addendum to ICRP Publication 72 concerning age-dependent doses to members of the public from intakes of radionuclides.

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.

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