<abstract xmlns="http://www.w3.org/1999/xhtml"><p>The aim of this work was to create a numerical model of scintillation detector and to check whether such detector can be used for the measurements of internal contamination in emergency conditions. The purpose of the measurements would be only detection of possible contamination, without identification of radioactive isotopes, and hence without estimation of effective dose. However, in emergency conditions, it is sufficient for the rapid selection of a group of contaminated persons, who should be subjected to careful inspection in the laboratory conditions. The calculations were performed for three detector positions relatively to the phantom. The distribution of dose rate was also calculated, in order to find the best geometry for dose rate measurements around human body. Another problem under consideration was the possible influence of radioactive contamination in the environment on the registration of the gamma spectrum emitted from the whole body phantom. Performed calculations showed that there is a possibility to measure internal contamination outside laboratory, even in contaminated area.</p></abstract>

The aim of this work was to create a numerical model of scintillation detector and to check whether such detector can be used for the measurements of internal contamination in emergency conditions. The purpose of the measurements would be only detection of possible contamination, without identification of radioactive isotopes, and hence without estimation of effective dose. However, in emergency conditions, it is sufficient for the rapid selection of a group of contaminated persons, who should be subjected to careful inspection in the laboratory conditions. The calculations were performed for three detector positions relatively to the phantom. The distribution of dose rate was also calculated, in order to find the best geometry for dose rate measurements around human body. Another problem under consideration was the possible influence of radioactive contamination in the environment on the registration of the gamma spectrum emitted from the whole body phantom. Performed calculations showed that there is a possibility to measure internal contamination outside laboratory, even in contaminated area.

Numerical model of detector for in vivo internal dosimetry in radiological incidents

National Centre for Nuclear Research, Otwock-Świerk, Sołtana 7, Poland

Polish Journal of Medical Physics and Engineering

The aim of this work was to create a numerical model of scintillation detector and to check whether such detector can be used for the measurements of internal...

Numerical model of detector for in vivo internal dosimetry in radiological incidents

Publié en ligne: 29 mars 2013

Pages: 29 - 39

DOI: https://doi.org/10.2478/v10013-012-0005-z

Mots clés
radiation protection, numerical modeling, MCNPx, FLUKA

This content is open access.

Numerical model of detector for in vivo internal dosimetry in radiological incidents

Publié en ligne: 29 mars 2013

Pages: 29 - 39

DOI: https://doi.org/10.2478/v10013-012-0005-z

Mots clésradiation protection, numerical modeling, MCNPx, FLUKA

This content is open access.

Mots clés
radiation protection, numerical modeling, MCNPx, FLUKA