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International Atomic Energy Agency Internal Dosimetry Software ASSESSMENT OF OCCUPATIONAL EXPOSURE DUE TO INTAKES OF RADIONUCLIDES.

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Presentation on theme: "International Atomic Energy Agency Internal Dosimetry Software ASSESSMENT OF OCCUPATIONAL EXPOSURE DUE TO INTAKES OF RADIONUCLIDES."— Presentation transcript:

1 International Atomic Energy Agency Internal Dosimetry Software ASSESSMENT OF OCCUPATIONAL EXPOSURE DUE TO INTAKES OF RADIONUCLIDES

2 International Atomic Energy Agency Introduction

3 International Atomic Energy Agency Internal dosimetry software Internal dosimetry related calculations are complicated  Biokinetic models  Dosimetric models  Direct measurement system calibrations Several software packages have been developed to assist the dosimetrist

4 International Atomic Energy Agency Software is available for various tasks Lookup tables  Dose coefficients  Retention fractions, etc. Dosimetry calculations  Intake  Committed equivalent dose  Committed effective dose

5 International Atomic Energy Agency Dose Coefficients and Intake Fractions

6 International Atomic Energy Agency Rad_toolbox Available, free of charge at This toolbox provides ready access to data of interest in radiation protection of workers and members of the public. Data include interaction coefficients for , e-, photon and n radiations, nuclear decay data, biological and physiological data, etc. Other supportive data include dose coefficients for intakes of radionuclides, for inhalation, ingestion for members of the public and workers. The ORNL TM report is included in the download.

7 International Atomic Energy Agency Rad_toolbox Dose coefficient workers ex ICRP 68

8 International Atomic Energy Agency Rad_toolbox Contains dose coefficients for single organs (committed equivalent dose) and Committed effective dose. There is the possibility to transfer the values on an Excel file Dose coefficients for workers

9 International Atomic Energy Agency Rad_toolbox Dose coefficients for members of the population

10 International Atomic Energy Agency ICRP Database of Dose Coefficients Contains dose coefficients from ICRP Publications 68 (Workers) and 72 (public), including organ doses Inhalation of 10 different AMADs 10 different integration periods Text of ICRP 68 and 72 with search function Biokinetic models for all elements Results can be saved as ASCII files and printed

11 International Atomic Energy Agency ICRP Database of Dose Coefficients

12 International Atomic Energy Agency ICRP Database of Dose Coefficients

13 International Atomic Energy Agency ICRP Database of Dose Coefficients Characteristics of output

14 International Atomic Energy Agency ICRP Database of Dose Coefficients On line help tool: Biokinetic model

15 International Atomic Energy Agency C. Potter: Health Physics retention fraction CD Pathway : Only Inhalation Retention/ excretion curves in table form CD-ROM attached to HP Nov issue, Vol. 83 n. 5 Intake retention fraction for stable element for respiratory tract, 24h urine, 24h feces, accumulated urine and accumulated feces (useful for 3 day collection of feces). Absorption Types F, M, S; 5 μm AMAD. No dose coefficients !

16 International Atomic Energy Agency C. Potter: Health Physics Intake retention fraction

17 International Atomic Energy Agency C. Potter: Health Physics retention fraction CD HP Vol 83, 5 Nov Biokinetic model parameters

18 International Atomic Energy Agency IAEA SRS 37 Available, free of charge at www-pub.iaea.org/MTCD/publications/PDF/Pub1190/Pub1190_web.pdf Tables : www-pub.iaea.org/MTCD/publications/PDF/Pub1190/tables.pdf Characteristics Pathway : Inhalation, ingestion, injection. Absorption types, F, M, S, V. AMAD = 1 and 5 μm. Vapors Tables in logarithmic intervals.

19 International Atomic Energy Agency IAEA SRS 37 Standard worker Sub-set of radionuclides present in ICRP 68

20 International Atomic Energy Agency IAEA SRS 37 Retention / excretion function (also skeleton organ) Dose coefficients for both inhalation, ingestion, injection.

21 International Atomic Energy Agency DCAL Available, free of charge at DCAL is a comprehensive software system for the calculation of tissue dose and subsequent health risk from intakes of radionuclides or exposure to radionuclides present in environmental media. The system includes extensive libraries of biokinetic and dosimetric data and models representing the current state of the art. DCAL maybe used either in an interactive mode or in a batch mode and is intended for experienced users with knowledge of computational dosimetry.

22 International Atomic Energy Agency DCAL

23 International Atomic Energy Agency DCAL Activity in organs Rate of equivalent dose in organs

24 International Atomic Energy Agency DCAL Committed organ doses and committed effective dose

25 International Atomic Energy Agency Dose Calculation Software

26 International Atomic Energy Agency Dose calculation software Software that can be used to estimate intake and internal doses has been developed using various techniques for different applications Table look-up Biokinetic and dosimetric modeling  Inhalation  Inhalation or ingestion  Single intake  Multiple intake

27 International Atomic Energy Agency MONDAL3 Available free of charge, on request at

28 International Atomic Energy Agency MONDAL3 Calculates intake and committed effective doses a point at a time. Several radionuclides Selection between Inhalation and ingestion Selection between workers and members of the population Mode of intake, acute, chronic, uneven chronic. m(t) values up to 1000 days after intake Radioinuclide available 3 H, 32 P, 51 Cr, 54 Mn, 59 Fe, 57 Co, 58,60 Co, 65 Zn, 86 Rb, 85 Sr, 89,90 Sr, 95 Zr, 106 Ru, 110m Ag, 124 Sb, 125 Sb, 125,129,131 I, 134,137 Cs, 140 Ba, 141,144 Ce, 203 Hg, 226,228 Ra, 228,232 Th, 234,235,238 U, 237 Np, 238,239,240 Pu, 241 Am, 242,244 Cm and 252 Cf. Selection of AMAD = 0.1, 0.3, 1.0, 3.0, 5.0 e 10 µm for workers = 1.0 µm for member of the population

29 International Atomic Energy Agency MONDAL3 Uneven chronic intake

30 International Atomic Energy Agency MONDAL3 m(t) value Evaluated intake I = M / m(t) E(50) = e(50) * IM = measurement value Type of measurement t = time of measurement

31 International Atomic Energy Agency Integrated Modules for Bioassay Analysis IMBA Development began in 1997 by the NRPB Features modular structure, interacting via ASCII data sets Implements latest ICRP biokinetic models Fitting uses maximum likelihood method  Use data recorded a being less than some minimum detection level  Specify multiple intake regimes

32 International Atomic Energy Agency IMBA Each module developed independently by two separate organizations Available in four different editions depending on included additional functions  Multiple intake regimes  Up to 30 associated nuclides  Simultaneous bioassay types

33 International Atomic Energy Agency IMBA Professional Plus Present status: IMBA Professional Plus

34 International Atomic Energy Agency IMBA Information available at tware/imbapro_plus/index.htm

35 International Atomic Energy Agency IMBA Information

36 International Atomic Energy Agency IMBA Bioassay calculation

37 International Atomic Energy Agency IMBA Use of multiple data-set for unique evaluation via maximum likelihood From Bioassay to intake From Intake to Bioassay

38 International Atomic Energy Agency IMBA Dose Calculations

39 International Atomic Energy Agency AIDE AIDE (Activity and Internal Dose Estimates) is a software for calculating activities in compartments and committed doses due to occupational exposures, and for performing intake and dose estimates using bioassay data This software has been continuously developed and tested for more than twenty years. Due to its extensive previous uses and challenges AIDE has proved to be suitable to all sorts of users, from beginners in internal dosimetry through its use in courses promoted by IAEA ARCAL (Harmonization of Internal Dosimetry Procedures (ARCAL LXXVIII),) up to advanced users performing evaluations of dose reconstruction.

40 International Atomic Energy Agency AIDE This software comprises three basic parts, which will be briefly described below: Activity and Internal Dose Calculations, Bioassay Interpretation, and Edit Models.

41 International Atomic Energy Agency AIDE Activity and internal dose calculations It has the aim to calculate activities in compatments and committed doses due to occupational exposure for performing intake and dose estimates using bioassay data

42 International Atomic Energy Agency AIDE Bioassay interpretation, intake evaluation chi squared test for fitting, possibility to de-select bioassay values.

43 International Atomic Energy Agency AIDE The Model Editing form: Possibility to edit different model from default ICRP models

44 International Atomic Energy Agency AIDE Detail of an original model: Source->Target fractions and biological half lives A demonstration of AIDE will be performed next week.

45 International Atomic Energy Agency IDEA - System Developed as spin-off project of the Research Center Karlsruhe. Expert system. Based on IDEAS Guidelines.

46 International Atomic Energy Agency Software Information Contacts RAD_Toolbox ICRP Database of Dose Coefficients C. Potter. Intake retention fraction Health Physics Sellers of Health Physics

47 International Atomic Energy Agency Software Information Contacts DCAL MONDAL3 IMBA lus/index.htm

48 International Atomic Energy Agency Software Information Contacts IAEA SRS 37 Pub1190_web.pdf DCAL MONDAL3

49 International Atomic Energy Agency Software Information Contacts IMBA lus/index.htm AIDE Rodolfo Cruz-Suarez at IAEA IDEA-System


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