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Spectrometric measurements of radioisotope activity in the thyroid

100%
Osko J., Golnik N.
Polish Journal of Medical Physics And Engineering
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2008
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vol. 14
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issue 3
123-134
EN
The results of measurements of iodine 131I and technetium 99mTc uptake in human thyroid, performed with scintillation or semiconductor detectors can exhibit a considerable uncertainty due to the differences in the thyroid position in the patient's neck. Basic physical laws of radiation attenuation and scattering show that the final shape of the registered spectrum should depends on the thyroid position in the neck and on the thickness of the tissue between the thyroid and the detector. The use of the spectrometric measuring method is proposed in this work for determination of the iodine gathering effective depth. The performed studies showed that the measurements results can be used for improving the accuracy of the iodine 131I activity in thyroid measurements and for selection of the group of patients for whom the anatomical position of the thyroid or the spatial distribution of the iodine gathering is much different than the standard one, assumed during the calibration of the counters. The results of the measurements were in agreement with Monte-Carlo calculations of the detector response. The method was used in routine monitoring of occupationally exposed persons, using the thyroid counter. A group of six persons with measurable internal contamination was selected and the measurements were performed on consecutive days, so the results could be registered at decreasing iodine activities in the thyroid. Larger series of measurements were performed at Brodno Regional Hospital in Warsaw, for a group of 95 patients after diagnostic administration of iodine 131I.
2
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IRPA initiative on radiation protection culture

100%
Golnik N., Tulik P.
Polish Journal of Medical Physics And Engineering
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2011
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vol. 17
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issue 1
1-12
EN
The concept of radiation protection culture, proposed by French Society for Radiation Protection (SFRP) and then launched by International Radiation Protection Association (IRPA) is presented. The paper is focused on the role of radiation culture in preventing unjustified fear associated with the use of radiation. Principles of RP culture and optimization of radiation protection, as well as the problems how RP culture can be learned and how to engage the stakeholders are considered.
3
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A Method of determination of ambient quality factor of fast neutrons in mixed radiation fields using advanced recombination methods

81%
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.
4
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Application of recombination chambers for determination of neutron ambient dose equivalent at the door to the maze of linear accelerator vault

81%
Jakubowska E., Golnik N., Gryzinski M., Tulik P.
Polish Journal of Medical Physics And Engineering
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2011
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vol. 17
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issue 3
153-158
EN
Recombination chambers and 2202D Studsvik-Alnor reference remmeter were used for determination of ambient dose equivalent, H*(10) and its neutron and gamma components at the door to the maze of 15 MV medical accelerator. The measurements were performed at opened and partly closed door. The results showed that the ambient dose equivalent rate was 76.2 μSv h-1 at the opened door and only 2.7 μSv h-1 at slightly opened door, 2.5 m from the entrance to the maze.
5
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Concept of a BNCT line with in-pool fission converter at MARIA reactor in Swierk

81%
Pytel K., Andrzejewski K., Golnik N., Osko J.
Polish Journal of Medical Physics And Engineering
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2009
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vol. 15
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issue 4
209-214
EN
BNCT facility in the Institute of Atomic Energy in Otwock-Swierk is under construction at the horizontal channel H2 of the research reactor MARIA. Measurements of the neutron energy spectrum performed at the front of the H2 experimental channel, have shown that flux of epithermal neutrons (above 10 keV) at the BNCT irradiation port was below 109 n cm-2 s-1 i.e. it was too low to be directly used for the BNCT treatment. Therefore, a fission converter will be placed between the reactor core and the periphery of the graphite reflector of MARIA reactor. The uranium converter will be powered by the densely packed EK-10 fuel elements with 10% enrichment. Preliminary calculations have shown that the total neutron flux in the converter will be about 1013 n cm-2 s-1 and flux of epithermal neutrons at the entrance to the filter/moderator of the beam will be about 2·1013 n cm-2 s-1.
6
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Measurements of high level of iodine activity in thyroid with different radiation meters

61%
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.
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