AIDE is a software for calculations of activities in compartments and committed dose estimates due to occupational exposures, and intake and dose estimates using bioassay data.
 
This software has been solely prepared by Dr. Luiz Bertelli. Part of it was initially meant to be used as a training tool in Internal Dosimetry. Every effort has been made to reproduce the original predicted values of the measured quantities following a single intake and the Dose Coefficients published by ICRP. However, minor differences might be noted since the calculation methods used in this software differ from those used to derive the original ICRP tables.

Biokinetic models and associated radioactive decay data are available for the following elements listed in ICRP Publication 78: H, Fe, Co, Sr, Ru, I, Cs, Ra, Ra, Th, Th, U, Np, Pu, Am, Cm, Cf. Predicted monitoring data tables for inhalation and ingestion associated with their most important isotopes, as appear in the ICRP Publication 78 tables, are available. Similar data have also been added for other important elements used in medicine, such as: Tc, P, S, C, Sm, Re, Po and Pb. In this way, the calculation of internal doses and interpretation of intakes for any isotope of the listed elements is already possible. In order to help the user predicted values of the measured quantities following single intake and associated dose coefficients are already available for the most common forms of occupational intakes of the following radionuclides: H-3, F-18, Fe-59, Co-57, Co-58, Co-60, Sr-85, Sr-89, Sr-90, Ru-106, I-125, I-129, I-131, Cs-134, Cs-137, Ra-226, Ra-228, Th-228, Th-232, U-234, U-235, U-238, Np-237, Pu-238, Pu-239, Pu-240, Am-241, Cm-242, Cm-244, Cf-252, Tc-99m, P-32, S-35, C-14, Sm-153, Re-188, Po-210 and Pb-210.

As an additional feature calculations of activities and doses can be promptly carried out for the complete list of gases and vapors shown in the ICRP Supporting Guidance 3 Publication. 

The latest highlight was the inclusion of the Wound Model recently proposed by the American National Council on Radiation Protection & Measurements (NCRP), which shows seven categories to characterize the retention of radionuclides in the wounds, namely: weak soluble, moderate soluble, strong soluble, avid soluble, colloid, particle and fragment.

It must be pointed out that besides having the biokinetic models for the isotopes listed above this software allows the user to enter any biokinetic model and associate any isotope whose decay scheme is available in ICRP Publication 38. Predicted values of measured quantities and corresponding equivalent doses can be calculated and stored in tables for later use in bioassay interpretation. This feature together with the ability to simulate inhalation cases using any AMAD, any set of mechanical transport parameters and any set of compound specific absorption parameters makes it particular powerful and useful in site-specific dosimetry applications.

This software has been continuously developed and tested for more than twenty five years. Its calculation core has been applied in several situations in internal dosimetry ranging from dose estimates due to Cs-137 intakes, which occurred during the Goiania accident, through modeling data from intakes of uranium trioxide and octoxide. The last important application of this software, which needs to be highlighted, was to produce the tables and plots of activities in compartments and dose coefficients as a function of time using the NCRP Wound Model. This NCRP report (NCRP Report no. 156.) is named “Development of a Biokinetic Model For Radionuclide-contaminated Wounds and Procedures for Their Assessment, Dosimetry and Treatment”.

Some publications, whose results were produced using this software, have been added to the “Selected Publications Where Previous Versions of This Software Have Been Used” section below. Several new features have been implemented in this version, which have been fully tested but might eventually show some discrepancies with results calculated by other authors.

This software comprises three basic modules:

A) Activity and Internal Dose Calculations: calculations of activities in bioassay compartments and effective doses for inhalation, ingestion and injection of radionuclides, for single, several, continuous and worker’s intake patterns, for infinite or limited time under intake. For the case of inhalation, vapors and gases have also been included besides particulate matter. The case of injection was considerably expanded with the inclusion of the Wound Model recently proposed by NCRP.

B) Bioassay Interpretation: intake and internal dose estimates can be carried out through the use of single or multiple bioassay measurements. All estimate procedures are in accordance with the methods presented in the ICRP-78 Publication, in the IAEA Safety Reports Series no. 37 and in the IDEAS Project Guidelines 2006.

C) Edit Models: it allows the user to view all parameters used in the biokinetic models to produce the tables of predicted values of the measured quantities following single intake and corresponding dose coefficients, which are available in this software. It also allows the user to enter, edit and erase own biokinetic models to be used in similar calculations.

Selected Publications Where Previous Versions of This Software Have Been Used.

1) Age-dependent Cs-137 Biological Half-lives Under the Effect of "Prussian Blue" in the Goiania Accident (Bertelli, L., Lipsztein, J.L.), Health Physics abstracts, Health Physics, Vol. 54, Supplement 1, 1988.

2)   An Analytical Mathematical Method to Calculate Activity in Body Organs and Excreta (Bertelli, L., Lourenco, M.C., Oliveira, C.A.N., Lipsztein, J.L.), Proceedings of an International Seminar on the Application of Computer Technology to Radiation Protection, IAEA-SR-136/52, 1989.

3)   Pharmacokinetic Models Relevant to Toxicity and Metabolism for Uranium in Humans and Animals (Wrenn, M.E., Lipsztein, J.L., Bertelli, L.), Radiation Protection Dosimetry, Vol, 26, 1/4, 1989.

4)   Internal Cs-137 Contamination in the Goiania, Brazil Accident (Bertelli, L., Lipsztein, J.L., Oliveira, C.A.N., Melo, D.R.), Proceedings of the Conference on the Medical Basis for Radiation Accident Preparedness, North Holland, 1989.

5)   Proposal for Optimization in the Interpretation of Bioassay Data for Workers Exposed to Internal Contamination, Ph.D. Thesis, (in Portuguese) Instituto de Biofisica Carlos Chagas Filho, Federal University of Rio de Janeiro, 1990.

6)   Studies of Cesium Retention in the Human Body Related to Body Parameters and Prussian Blue Administration (Lipsztein, J.L., Bertelli, L., Oliveira, C.A.N., Dantas, B.M.), Health Physics, Vol. 60, no.1, pp.43-49, 1991.

7)   Influence of Tissue Weighting Factors on Risk Weighted Dose Equivalent Quantities (Bertelli, L., Nascimento, J.E.C., Drexler, G.), Radiation Protection Dosimetry, Vol. 37, no. 2, 1991.

8)   A Case Study of the Transfer of Cs-137 to the Human Fetus and Nursing Infant (Bertelli, L., Oliveira, C.A.N., Lipsztein,. J.L., Wrenn, M.E.), Radiation Protection Dosimetry, Vol. 41, nos. 2-4, 1992.

9)   A Comprehensive Metabolic Model for Uranium Metabolism and Dosimetry Based on Human and Animal Data (Wrenn, M.E., Bertelli, L., Durbin P.W., Singh, N.P., Lipsztein, J.L., Eckerman, K.F.), Radiation Protection Dosimetry, Vol. 53, nos. 1-4, 1994.

10) Interpretation of In Vivo and Bioassay Results and Dose and ALI Calculations Using a New Uranium Model (Bertelli, L., Wrenn, M.E.), Radiation Protection Dosimetry, Vol. 53, nos. 1-4, 1994.

11) Cs-137 Internal Contamination of Members of the Public Involved in an Accident in Brazil and the Efficacy of Prussian Blue Therapy (Melo D.R., Lipsztein J.L., Oliveira C.A.N., Bertelli L.), Health Physics, Vol. 66, no.3, pp 245-251, 1994.

12) A Biokinetic and Dosimetric Model for the Metabolism of Uranium, (M.E. Wrenn, L. Bertelli, P.W. Durbin, K.F. Eckerman, J.L. Lipsztein, N.P. Singh), AECB Report INFO Series 500, Atomic Energy Control Board, Ottawa, Canada, 1995.

13) Interpretation of Bioassay Measurements Using Different Systemic Models for Plutonium, (L. Bertelli , M.E. Wrenn), Journal of Radioanalytical and Nuclear Chemistry, Vol. 197, no. 1, 67-78 (1995).

14) Modified Respiratory Tract Model for Uranium: Its Implications on Bioassay Interpretations, (M.E. Wrenn, L. Bertelli), Journal of Radioanalytical and Nuclear Chemistry, Vol. 197, no. 1, 196-202 (1995).

15) Specific Absorption Parameters for Uranium Octoxide and Dioxide: Comparison of Values Derived from Human Data and Those Predicted from Animal Studies (Bertelli L.,  Puerta A., Wrenn M.E., Lipsztein J.L., Moody J.C., Stradling G.N., Hodgson A. and Fell T.P.) Radiation Protection Dosimetry, Vol. 79, nos. 1-4, 87-90, 1998.

16) Bioassay Interpretation and Dosimetry Using Specific Absorption Parameters For UO2 and U3O8 (Bertelli L., Puerta A., Wrenn M.E., Lipsztein J.L.) Radiation Protection Dosimetry, Vol. 79, nos. 1-4, 111-113, 1998

17) Sensitivity of Doses and Associated Uncertainties in Bioassay Estimates to ICRP Publication 66 Respiratory Tract Dosimetric Model With Respect to the Parameters: Ventilation Rates, Time Budget, Total and Regional Deposition, Oral versus Nasal Breathing and Clearance Rates of Compartments (Bertelli, L., Guilmette, R.A., Singh, N.P.) Journal of Radioanalytical and Nuclear Chemistry, Vol. 252, No.2, 327-338, Akademiai Kiado, Budapest, Hungary and Kuwer Academic Publishers, Dordrecht, The Netherlands, 2002.