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EN
Boron Neutron Capture Therapy is a very promising form of cancer therapy, consisting in irradiating a stable isotope of boron (10B) concentrated in tumor cells with a low energy neutron beam. This technique makes it possible to destroy tumor cells, leaving healthy tissues practically unaffected. In order to carry out the therapy in the proper way, the proper range of the neutron beam energy has to be chosen.In this paper we present the results of the calculations, using the MCNP code, aiming at studying the energetic dependence of the absorbed dose from the neutron capture reaction on boron (the therapeutic dose), and hydrogen and nitrogen (the injuring dose).
EN
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.
EN
Trynitite is a material in form of a glass created as a result of a nuclear explosion close to ground. The mechanism of its formation is similar to the formation of impact glasses and tektites, although the material usually contains trapped bubble voids, much more water and it is radioactive. High resolution non-destructive gamma spectrometry technique was used to measure rdionuclides in the chips of trinitities. The signals were detected for 137Cs, 152Eu, 226Ra, 241Am and 133Ba. The most extreme concentration was found for cesium 137Cs which the specific activity reached the level of 2317 mBq/g. Much lower values were obtained for 241Am – 722 mBq/g, 152Eu – 211 mBq/g, 226Ra – 451 mBq/g and 133Ba – 94 mBq/g.
EN
Radioactive cobalt isotope 60Co is produced in neutron activation process of stable isotope 59Co by neutron capture reaction 59Co(n,g)60Co, in solar wind charge exchange 60Ni(n,p)60Co or in spallation process 62Ni(n,p2n)60Co. These processes are responsible for isotope 60Co production either in nuclear reactor on Earth or beyond – in stars and in meteorites (induced by cosmic rays). In this work the results of 60Co measurements in metal sources by gamma spectrometry laboratory are presented. A metal reference radioactive standards made up of steel cast with discs shaped geometries and different diameters have been tested in gamma-ray spectrometry measurement system. The reference activity concentrations of 60Co were in the range of (0.291±0.010) Bq·g–1 to (1.544±0.030) Bq·g–1. The mean minimal detectable activities (MDA) obtained by series of the 6 to 18 hours lasting measurements of described above standards with HPGe detectors carried out in NCBJ OR POLATOM were in the range of 6.1 mBq·g–1 to 8.5 mBq·g–1. The results correspond to the values of 60Co activity concentration measured in the iron meteorites with young terrestrial ages.
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