DOSIMETRIC EVALUATION OF NATURAL AND ARTIFICIAL RADIOACTIVITY IN ENVIRONMENT USEFUL FOR FORENSIC PURPOSES

Authors

  • Marija Janković Vinča Institute of Nuclear Sciences, National Institute of the Republic of Serbia, University of Belgrade
  • Jelena Krneta Nikolić Vinča Institute of Nuclear Sciences, National Institute of the Republic of Serbia, University of Belgrade, Mike Petrovića Alasa 12-14, 11001 Belgrade, Serbia
  • Marija Šljivić-Ivanović Vinča Institute of Nuclear Sciences, National Institute of the Republic of Serbia, University of Belgrade, Mike Petrovića Alasa 12-14, 11001 Belgrade, Serbia
  • Nataša Sarap Vinča Institute of Nuclear Sciences, National Institute of the Republic of Serbia, University of Belgrade, Mike Petrovića Alasa 12-14, 11001 Belgrade, Serbia
  • Filip Veljković Vinča Institute of Nuclear Sciences, National Institute of the Republic of Serbia, University of Belgrade, Mike Petrovića Alasa 12-14, 11001 Belgrade, Serbia
  • Milica Ćurčić Vinča Institute of Nuclear Sciences, National Institute of the Republic of Serbia, University of Belgrade, Mike Petrovića Alasa 12-14, 11001 Belgrade, Serbia
  • Bojan Janković Vinča Institute of Nuclear Sciences, National Institute of the Republic of Serbia, University of Belgrade, Mike Petrovića Alasa 12-14, 11001 Belgrade, Serbia

Keywords:

exposure to ionizing radiation, dosimetric quantities, radiation detectors, NORM

Abstract

Purpose: The primary purpose of this study is to investigate the mechanism of exposure to ionizing radiation through different pathways with a focus on both external and internal exposure scenarios. By examining the behavior and distribution of natural and artificial radionuclides in different matrices, the research aims is to quantify absorbed, equivalent, and effective doses relevant to human exposure. Special emphasis is placed on the forensic relevance of radiation dose assessment and its application in identifying sources and situations of exposure using radiation detection methods. The use of radiation detectors and dosimetric methods ensures accurate detection and analysis, making the results applicable to radiation protection.Design/Methods/Approach: This paper presents a study about dosimetric quantities that can be derived from radionuclide concentration data in various matrices. The focus is placed on understanding the relationship between radionuclide activity concentrations and the calculation of key dosimetric quantities, including absorbed dose, equivalent dose and effective dose. The approach involves reviewing existing methodologies and mathematical models used for dose estimation based on internal and external exposure scenarios.

Findings: Various dosimetric quantities, such as absorbed dose, equivalent dose and effective dose can be estimated based on radionuclide activity concentrations in different media. These quantities are essential for assessing both external and internal exposure to ionizing radiation. This framework enables dose assessments based on contamination data. The findings underline the importance of combining radiological measurements with dose modeling tools in order to support health risk assessment.

Originality/Value: This paper provides a structured overview of how key dosimetric quantities can be determined from radionuclide concentration data, without direct dosimetric measurements and emphasis on the role of nuclear techniques and dose assessment methodologies as fundamental tools in forensic analysis, in the context of radiological or nuclear emergencies. This study provides a valuable reference for professionals involved in dose assessment and ionizing radiation protection. 

 

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Published

2026-03-26

Issue

Section

Natural and Applied Sciences in Forensics, Cybercrime and Security