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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.
2
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Assessment of occupational internal exposure to beta emitters from the nuclear reactor primary coolant circuit

71%
Pliszczyński T., Ciszewska K., Dymecka M., Ośko J., Haratym Z.
Polish Journal of Medical Physics And Engineering
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2012
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vol. 18
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issue 2
41-47
EN
Fission products of 235U or isotopes from activation may appear in technological waters at normal operation of a research reactor. Therefore, reactor cooling water may contain a number of beta radioactive isotopes including yttrium and strontium isotopes, which can pose potential hazard to reactor personnel. In order to asses internal exposure urinalysis is carried out. This work presents the method of sample preparation and measurement used by Radiation Protection Measurements Laboratory (RPLM) of the National Centre for Nuclear Research (NCNR). Method of various isotopes of yttrium and Sr-90 activity calculation is also shown. Determination of these isotopes activities in urine sample allows estimating the effective doses
3
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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.
4
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Estimation of internal radiation exposure using a whole body counter

61%
Pliszczyński T., Ośko J., Ciszewska K., Haratym Z., Umaniec M., Sosnowiec R.
Polish Journal of Medical Physics And Engineering
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2011
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vol. 17
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issue 4
163-171
PL
Proces oceny narażenia wewnętrznego na skażenia substancjami promieniotwórczymi jest skomplikowany i towarzyszy mu wiele czynników, które są źródłem niepewności szacowania obciążającej dawki efektywnej. W niniejszym artykule przedstawiono sposób właściwego postępowania podczas szacowania obciążającej dawki efektywnej za pomocą Licznika Promieniowania Ciała Człowieka.
EN
Estimation of internal radiation exposure using a whole body counter
5
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Validation of the method for determination of plutonium isotopes in urine samples and its application in a nuclear facility at Otwock

61%
Rzemek K., Czerwiński A., Dymecka M., Ośko J., Pliszczyński T., Haratym Z.
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issue 1
181-186
EN
The studies aimed at determining low activities of alpha radioactive elements are widely recognized as essential for the human health, because of their high radiotoxicity in case of internal contamination. Some groups of workers of nuclear facility at Otwock are potentially exposed to contamination with plutonium isotopes. For this reason, the method for determination of plutonium isotopes has been introduced and validated in Radiation Protection Measurements Laboratory (LPD) of the National Centre for Nuclear Research (NCBJ). In this method the plutonium is isolated from a sample by coprecipitation with phosphates and separated on a AG 1-X2 Resin. After electrodeposition, the sample is measured by alpha spectrometry. Validation was performed in order to assess parameters such as: selectivity, accuracy (trueness and precision) and linearity of the method. The results of plutonium determination in urine samples of persons potentially exposed to internal contamination are presented in this work.
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