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1.
Radiat Prot Dosimetry ; 105(1-4): 219-23, 2003.
Article in English | MEDLINE | ID: mdl-14526959

ABSTRACT

The aim of this paper is to describe the dosimetric evaluation of a point contamination that occurred in a laboratory during the examination of an irradiated sample. The incident led to point contamination of the operator's finger due to the presence of mainly 106Ru, with its progeny, 106Rh. The paper reports on the activity and dose assessment, performed using several methods. The measured activity was obtained using a conventional device based on a germanium detector and confirmed using software developed at IRSN, based on reconstruction of voxel phantom associated with the Monte Carlo N-Particle code (MCNP) for in vivo measurement. Two dose assessment calculations were performed using both analytical and Monte Carlo methods, applying the same approach as for activity assessment based on the personal computational phantom of the finger. The results are compared, followed by a discussion on the suitability of the tools described in this study.


Subject(s)
Finger Injuries/metabolism , Models, Biological , Radiometry/methods , Rubidium Radioisotopes/administration & dosage , Rubidium Radioisotopes/pharmacokinetics , Wounds, Penetrating/metabolism , Computer Simulation , Finger Injuries/pathology , Humans , Image Interpretation, Computer-Assisted/methods , Phantoms, Imaging , Radiation Dosage , Radioactive Hazard Release , Radiometry/instrumentation , Rubidium Radioisotopes/analysis , Wounds, Penetrating/pathology
2.
Radiat Prot Dosimetry ; 105(1-4): 403-8, 2003.
Article in English | MEDLINE | ID: mdl-14526997

ABSTRACT

This paper reports on a new utility for development of computational phantoms for Monte Carlo calculations and data analysis for in vivo measurements of radionuclides deposited in tissues. The individual parameters of each worker can be acquired for an exact geometric representation of his or her anatomy, which is particularly important for low-energy gamma ray emitting sources such as thorium, uranium, plutonium and other actinides. The software discussed here enables automatic creation of an MCNP input data file based on computed tomography (CT) scanning data. The utility was first tested for low- and medium-energy actinide emitters on Livermore phantoms, the mannequins generally used for lung counting, in order to compare the results of simulation and measurement. From these results, the utility's ability to study uncertainties in in vivo calibration were investigated. Calculations and comparison with the experimental data are presented and discussed in this paper.


Subject(s)
Actinoid Series Elements/pharmacokinetics , Air Pollutants, Radioactive/pharmacokinetics , Lung/diagnostic imaging , Lung/metabolism , Models, Biological , Monte Carlo Method , Radiometry/methods , Actinoid Series Elements/analysis , Calibration , Computer Simulation , Feasibility Studies , Humans , Inhalation Exposure/analysis , Phantoms, Imaging , Quality Control , Radiation Dosage , Radiography , User-Computer Interface
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