Derived CDG for bioassay – a tool for screening people in a radiological emergency

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DOI:

https://doi.org/10.15392/bjrs.v9i3.1693

Keywords:

Radiological emergency, internal contamination, medical follow-up

Abstract

The decision on initiating clinical treatment for a person who has been internally contaminated by radionuclides is not trivial. NCRP Publication 161 presented an operational quantity named Clinical Decision Guide - CDG to help in this decision. The bases for establishing the CDG values are dose values related to the risks of stochastic and deterministic effects to body tissues. This work shows a computational system -  Derived CDG -  which calculates CDG and derived CDG applied to in vivo and in vitro radiobioassay for several age groups and for several times after intake by inhalation and ingestion. It is a tool to be used to screen people with internal contamination who need medical follow-up. The system enables the users to change parameters used in calculation for different simulated scenarios.

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Author Biography

Arlene Alves dos Reis, Instituto de Radioproteção e Dosimetria

Divisão de Dosimetria

 

References

National Council on Radiation Protection and Measurements. Management of persons contaminated with radionuclides: handbook. Recommendations of the National Council on Radiation Protection and Measurements, NCRP 161 I, (2008).

National Council on Radiation Protection and Measurements. Management of persons contaminated with radionuclides: scientific and technical bases. Recommendations of the National Council on Radiation Protection and Measurements, NCRP 161 II, (2008).

Medical Management of Persons Internally Contaminated with Radionuclides in a Nuclear or Radiological Emergency, EPR - Internal Contamination 2018, International Atomic Energy Agency, Viena, 2018.

Preparedness and Response for a Nuclear or Radiological Emergency, IAEA Safety Standards Series No. GSR Part 7, International Atomic Energy Agency, Viena, 2015.

A. A. dos Reis, L. Bertelli, W. O. Sousa – Evaluation of reference urinary excretion concentration of selected radionuclides corresponding to clinical decision guides for application in radiological and in nuclear emergency. Radiation Protection Dosimetry, Vol. 175, No. 1, pp. 134–148, doi:10.1093/rpd/ncw279, 2017.

Monitoring and Dose Assessment for Children Following a Radiation Emergency – Part I: Reference Values for In Vitro Bioassay. Health Physics, Vol.112 (3), pp. 282-293, 2017.

Halvorson M. Microsoft: Visual Basic 2010 – Passo a passo. Bookman, 2011.

Petroutsos E. Mastering Visual Basic 2010, Wiley Publishing, Indiana, 2010.

ICRP. International Commission on Radiological Protection Publication 72: Age-Dependent Doses to Members of the Public from Intake of Radionuclides (Part 5). Compilation of Ingestion and Inhalation Coefficients, in Annals of the ICRP 26(1) (1996).

ICRP. International Commission on Radiological Protection, ICRP-CD1: Database of Dose Coefficients: Workers and Members of the Public, Version 3.0, in Annals of the ICRP 26(1) (1996).

Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards Generic Safety, GSR Part 3, International Atomic Energy Agency (2015).

Eckerman KF, Leggett RW, Cristy M, Nelson CB, Ryman JC, Sjoreen AL, Ward RC. DCAL system dose and risk calculation system, version 8.4. Oak Ridge, TN: Oak Ridge National Laboratory; ORNL/TM2001/190; 2006.

ICRP. International Commission on Radiological Protection Publication 89: Basic Anatomical and Physiological Data for Use in Radiological Protection Reference Values, in Annals of the ICRP 32(3–4) (2002).

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Published

2021-09-20

How to Cite

Reis, A. A. dos. (2021). Derived CDG for bioassay – a tool for screening people in a radiological emergency. Brazilian Journal of Radiation Sciences, 9(3). https://doi.org/10.15392/bjrs.v9i3.1693

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