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The Comparison of Data of Current Radiation Situation with in Europe
STRÁNSKÝ, Petr
The aforesaid topic of this bachelor thesis was chosen mostly for the current issue of the radiation security, which importance will most likely rise in the future. That is why it should be taken more seriously. The purpose of this thesis was to compare the availability of data on the current radiation situation in different countries of Europe and at the same time to consider the clarity and the way of presenting the given facts online. Afterwards it was possible to answer the research question: "Are the data given by different countries comparable?" In the theoretical part of this thesis the author used the method of research by studying different literary sources. The crucial terms of the topic were defined, the sources of the ionizing radiation were described and this part also described the movement of the radioactive matter in the environment and its impact on human organism. Furthermore the author focused on the system of the monitoring of the radiation situation, mostly in the Czech Republic. Last but not least the thesis deals with the legislation of the radiation monitoring and also the exchange of data, mainly the European radiological data exchange platform (EURDEP). The outcomes of the thesis were gained by a comparative analysis of the websites which are focused on the radiation situation in different states. The results show, that most of the European countries are focused on continuous monitoring of the batch input. Other published data came mainly from the measurements of the radionuclide volume in the air, in particular from the measuring of the activity of aerosol and atmospheric fallouts. Other monitored items compared in this thesis were not so available. The clarity and the way of presenting these data online were quite various by different countries. The best compiled website was the Czech application MonRaS, which was the only of the compared sites which offered data of all the considered items of the radiation monitoring. The thesis will be used for further studies of the topic and can broaden the knowledge of the availability of radiation data online.
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A comparison of the radiometers which are used by the Fire Rescue Service of the Czech Republic
PETRŮV, Josef
Fire Rescue Service is the basic component of an integrated rescue system, with high working demands placed on their activity. The number of activities firefighter units perform is extensive; especially great attention is paid to interventions with eventual incidence of ionizing radiation. Ionizing radiation is not possible to detect by human senses, but is possible to detect with special instruments. Identification of ionizing radiation is not simple; it requires certain amount of time, professional knowledge, and facilities. To prevent irradiation of people who are present at an intervention place and also people who intervene, the units of Fire Rescue Service of the Czech Republic are equipped with the portable ionizing radiation detectors according to Conception of Chemical Service. These are namely DC-3E-98, DC-3H-08 and Ultra- Radiac (U-RAD 115). The instruments are constructed to detect radiation. The goal of the thesis is to compare instruments in terms of the accuracy and speed of measurement and to assess suitability of use of the instruments by fire protection units of the Czech Republic, economic comparison and the practicability of the instruments. DC-3E-98 is hand contamination detector used for surface contamination and dose rate meter that dates with its design back to 1970s of the series DC-3 used for operative radiological survey. It was developed and manufactured in today's nonexistent plant Zavod mechanizace a automatizace Ostrov nad Ohri. This device has been used until recent days after had been modified at the end of 1990s and because of needs to follow Act on Metrology. It is consisting of two parts, separate instrument and removable probe. Both parts create easily demountable unit allowing carrying out measuring by only one hand. Its great advantage is fast response and large-area probe with Geiger-Müller tube used as a detector. DC-3H-08 is the latest type coming out of type series DC-3 and was developed by the innovation of previous type DC-3E-98. This device was developed by the company VF a.s. Cerna Hora using financial sources coming from European Union for the Fire Rescue Service of the Czech Republic. It is the instrument with satisfactorily large display and robust construction suitable for measuring outdoors. It is consisting of two independent parts - indicator and basic units. When mounted together, the device works as complex, when separated, each unit can work independently and the communication between them is wireless using Bluetooth. The device is possible operate using four buttons at the indicator unit. It is possible to use the device for measuring kerma dose in the air, areal dose equivalent dosage, surface activity, accumulated dose and for checking people's contamination. The disadvantage of the device is its heavy weight and impossibility of controlling audio output, operating time (only 4 hours), and its high purchase price when compared to others. Ultra-Radiac (U-RAD115) is hand detector determined for indication of gama radiation sources, measuring dose rates, scheduling the time for people who intervene, setting-out safety zone for gama radiation and for direct data reading of accumulated dose. The device is company Canbera Dover Inc.' product. It is device of smaller size; its operation is actually easy and intuitive with the help of six buttons. It is suitable to be used outdoors because of its robustness. This device is recently sufficient for basic units HZS CR and when Canberra Packard finishes prototype stage of beta probe of this device for our market, it can fully replace device DC-3E that is recently serving out.
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A patient after a diagnostic application of radiopharmaceuticals as a source of radiation - mutual radiation strain of the personnel and patients
MARKOVÁ, Iveta
ABSTRACT A patient after a diagnostic application of radiopharmaceuticals as a source of radiation - mutual radiation strain of the personnel and patients My work focuses on the radiation protection on account of the potential influence of ionizing radiation with its negative effects on a human organism. In my work I concentrated on observing the obtained personal equivalent doses of the ionizing radiation in the Department of Nuclear Medicine in the Hospital of České Budějovice, plc. I also focused on the measurement and assessment of the dose rate obtained by the employees of the Department of Nuclear Medicine in the Hospital of České Budějovice, plc. from treated patients with regard to the distance and type of the applied radiopharmaceutical. The methods chosen for the actual measuring, gathering, recording and assessment of the data are described in a great detail and presented in the methodology of my work. The data obtained from the personal TL dosimeters is registered and filed in the Department of Nuclear Medicine in the Hospital of České Budějovice, plc. on a long term basis. Therefore it enabled me to analyze the equivalent dose of four nurses during the last five years. The results were compared with the figures determined in the regulation 307/2002 of the Code, as amended by regulation 499/2005 of the Code. The results are then clearly presented in tables and graphs. The collected data has confirmed that the values of equivalent doses obtained from the personal TL dosimeters of four nurses working in the Department of Nuclear Medicine in the Hospital of České Budějovice, plc. do not exceed figures determined by the regulation 307/2002 of the Code, as amended by regulation 499/2005 of the Code. The measured dose rates decrease with the distance and are proportional to the activity and type of radiopharmaceutical.
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Possibilities in Exploitation of Laboratory Equipment in Faculty of Health and Social Studies, University of South Bohemia
ONDROVÁ, Veronika
Bachelor thesis entitled Possibilities of measuring instruments in the laboratory ZSF JU is aimed at teaching personal dosimetry laboratory. In the introduction the problem of dosimetry - the types of ionizing radiation dosimetry tasks and objectives. Cooperation with other dosimetry disciplines and last but not least, the basic quantities and units that are used in dosimetry and radiation protection. The main objective was to develop a comprehensive overview of equipment and instrumentation in the laboratory personal dosimetry measurement and specify their characteristics. The following sections describe each personal dosimetry laboratory instruments - their general description, basic parts, setup, control, measurement procedures and equipment use in teaching.
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Measuring methods of surface contamination with radioactive substance in the nuclear power plant Temelin
PAPAN, Juraj
Monitoring of the occurrence and scope of surface contamination is performed by the Radiation Protection department in order to adopt adequate measures for the protection of persons from unwanted contamination and to inspect observation of limits for surface contamination and for items taken outside the controlled area. The chapter containing results and collected data includes a definition of the measured parameter and it stresses the surface contamination as a major health risk factor, which is demonstrated by conversion of surface contamination values into absorbed doses in the exposed body organs. This is followed by the principles, issues and factors affecting detection of ionizing radiation, particularly the surface activity, which is used to express the extent of surface contamination. The issues of detection are followed by a description of scope and principle of monitoring implementation within which the individual measurements are performed, taking into account the reference levels for specific measurements. The individual measuring procedures are accompanied with descriptions of their use. Apart from a summary description of the implementation of surface contamination monitoring in the nuclear power plant Temelín, one of the objectives of the thesis was the analysis of errors introduced into the measurement process by persons performing the measurements. The main objective of the thesis was to confirm the hypothesis that measures adopted by the Radiation Protection department, based on results from working measurements for the protection of workers who get into contact with radioactivity in form of surface contamination, are sufficient and that the limits for surface contamination of items taken outside the controlled area are not exceeded.
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The time slope of radioiodine retention in patients a few days after 131I curative dose administration
MACHÁČKOVÁ, Věra
After comparison diagnostic half time and therapeutic half time was found out bigger diference then established variation. It leads to result that therapeutic half time and indirect radioiodine retention too is depending on applicated activity. According the measurement I can establish the date of dismission in patients with benign thyroid gland disease on the second day (at lower therapeutic activity) and the tenth day (at higher therapeutic activity) after administration therapeutic dose. In patients with malign thyroid gland disease the date of dismission can be established on the third day (at lower therapeutic activity) and the fifth day (at higher therapeutic activity) after administration therapeutic dose.
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