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Measurements of high level of iodine activity in thyroid with different radiation meters

100%
Ośko J., Golnik N., Pliszczyński T., Sosnowiec R., Umaniec M., Zielczyński M.
Polish Journal of Medical Physics And Engineering
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2012
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vol. 18
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issue 1
1-6
EN
Iodine activity in thyroid of female patient was measured with different radiation meters in order to estimate a possibility to use them in case of radiation accident. Two series of measurements were performed - first after diagnostic and second after therapeutic administration of iodine to the patient. The isotope activities were higher than those registered during routine radiation monitoring and similar to the activities which could be registered after radiation accident. The studies showed that simple dose rate meters may serve for identification and selection of contaminated persons which should be later subjected to the measurements with especially dedicated equipment. The initial measurements can be performed outside laboratory.
2
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Numerical model of detector for in vivo internal dosimetry in radiological incidents

100%
Ośko J., Tymińska K.
Polish Journal of Medical Physics And Engineering
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2012
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vol. 18
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issue 2
29-39
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.
3
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Radiation Shielding Properties of Some Composite Panel

100%
Al-Sarray E., Akkurt İ., Günoğlu K., Evcın A., Bezır N.
Acta Physica Polonica A
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2017
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vol. 132
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issue 3
490-492
EN
With the discovering atomic nucleus, nuclear science started to be used in different fields and researcher focused on radiation protection as it is dangerous for human cell. Thus radiation physics and materials development becomes one of the important subject in science for this purposes. The developed material should be used for radiation shielding. In this work gamma ray shielding properties of some composite materials produced by polymer have been investigated.
4
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A Method of determination of ambient quality factor of fast neutrons in mixed radiation fields using advanced recombination methods

63%
Zielczyński M., Golnik N., Gryziński M.
Polish Journal of Medical Physics And Engineering
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2011
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vol. 17
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issue 4
189-206
PL
Przedstawiono sposób wyznaczania przestrzennego współczynnika jakości neutronów prędkich, Qn*(10), w polu promieniowania mieszanego o nieznanym, lecz ograniczonym, widmie energii neutronów. W tym sposobie wykorzystuje się korelacje między wartościami Qn*(10), obliczonymi metodą Monte Carlo dla neutronów monoenergetycznych, a parametrami doświadczalnych charakterystyk nasycenia komory rekombinacyjnej, umieszczonej we wzorcowych polach neutronów monoenergetycznych wraz z towarzyszącym promieniowaniem gamma. Omija się przy tym szereg niepewności, m.in. związanych z brakiem pełnej odpowiedniości między współczynnikiem jakości promieniowania a parametrami, od których zależy lokalna rekombinacja jonów, a także z brakiem pełnej odpowiedniości konstrukcji komory rekombinacyjnej z tzw. kulą MKJR (ang. ICRU) definiującą wielkości operacyjne H*(10) i Q*(10).
EN
The paper presents a method for determination of ambient quality factor for fast neutrons, Qn*(10), in mixed radiation fields with unknown neutron energy spectrum of limited energy range. The method uses a correlation between the Qn*(10) values, calculated by Monte-Carlo method for monoenergetic neutrons, with parameters of saturation curves of the recombination chamber, determined experimentally in the fields of monoenergetic neutrons and accompanying gamma radiation. In such a way, a number of discrepancies can be omitted, among them those associated with limited conformity between radiation quality factor and parameters of initial recombination of ions, as well as between construction of the recombination chamber and ICRU sphere, for which the quantities H*(10) and Q*(10) were defined.
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