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Ionizing radiation doses of the radiology assistants in the CT and PET/CT wards
MAZLOVÁ, Lenka
Hybrid methods, such as PET/CT, operating with the ionizing radiation, are being used more and more frequently, the number of wards working with this device increases in the Czech Republic. Just PET/CT belongs to the most modern imaging methods among them. In my thesis I compare the radiation doses to which the radiology assistants in the nuclear medicine ward and radiodiagnostics ward are exposed to. The part of the assessment is also the comparison of the radiation protection in the mentioned wards. From methodology point of view, I compared two wards, the hospital ``Na Homolce{\crqq}, where is situated the PET centre with the hybrid PET/CT device, and ``Úrazová nemocnice{\crqq}, equipped with the CT device. With the approval of the employees of the individual wards the data on the quantity of the examinations were processed for the period from 1. 1. 2008 to 30. 9. 2009. Data on the radiation doses were processed by the National Service of Personal Dosimetry in Prague. The number of staff in the individual wards varied during the monitored period, in common there were 13 people in each ward. Radiation load doses for each person were regularly registered during the monitored period. Dosimeters were used for the registration. The nuclear medicine ward uses personal and fingertip dosimeters. These are evaluated each month. On the contrary, the diagnostics ward - CT ward uses only personal dosimeters, evaluated once in three months. The values are presented in the tables. Comparing the personal dosimetry of the PET centre staff and the computer tomography staff, we come to the following results: Monitored period 1 and {$^3\!/\!_4$} year. Annual doses of the ionizing radiation per the person involved in the computer tomography can reach maximally 0,4mSv in the personal dosimetry. Doses per the representative of the PET centre equal to 2.88mSv per year for the personal dosimeters. The results confirmed the hypothesis assuming that the radiology assistants in the nuclear medicine ward are exposed to higher radiation load in comparison to the radiodiagnostics ward working with the CT device. The results comply with the limits for the radiation staff as stipulated in the notice 307/2002 Coll.
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Effect of New Positron Radiopharmaceutical Shielding Equipment on Radiation Load Reduction of PET Centre Personnel.
MAŇASOVÁ, Olga
The bachelor thesis focuses on radiation protection of nuclear medicine personnel while using positron radiopharmaceuticals. The thesis is aimed at evaluating efficient and equivalent doses of PET centre personnel at Na Homolce Hospital where new shielding equipment with an activity dosing device was installed in 2006. Positron radiopharmaceuticals are characterized by emission of 2 annihilation gamma photons of high energy (511 keV) that are created upon interaction of a positron with an electron. Due to the high energies, radiological personnel receives higher radiation loads than upon application of common, particularly technecium-based radiopharmaceuticals used in nuclear medicine. The methodology consists in comparing efficient and equivalent doses before and after installation of the new shielding equipment. On base of results we can state that the doses to personnel were significantly reduced after installation of new shielding equipment. The doses were reduced by half during three years. New shielding is relevant from optimalization of radiation protection perspective. Statistical processing and graphic illustrations form part of the bachelor thesis.
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The impact of mining and cultivation of uranium ore on the surroundings of the area of Dolni Rozinka
STRÁNSKÁ, Marta
Beginnings of uranium mining in the Czech Republic date back to 1945. At that time uranium mining developed rapidly and the demand for uranium ore rose. There were two new uranium deposits discovered near Rožná and Olší during the summer and autumn 1956, and in 1957 the excavation of R1 shaft near Rožná started. Since 1958 uranium ore has been mined from this deposit, located in the district of Žďár nad Sázavou in the Vysočina region. Nowadays it is the last exploited underground deposit of uranium in the Czech Republic. The end marketable product from the extraction and dressing process is uranium concentrate (so called yellow cake) in the form of ammonium diuranate and a by-product from the disposal of excess water from the dressing plant is marketable sodium sulphate. However, mining operations at the Rožná locality have affected the environment, caused changes in the relief, water regime, draining, vegetation and fauna. Moreover, this activity affected health and quality of life of miners, their families and all residents in this locality. Operations by GEAM Dolní Rožínka (a branch of the state enterprise DIAMO) and the impact on the environment is monitored in accordance with Section 18 of Act No 17/1992 on the environment. Annually, since 1990s, monitoring is conducted in accordance with documented monitoring programmes which are approved and their results discussed by the competent administrative authorities, professional supervisory bodies (the State Office for Nuclear Safety), and are available to the general public. Based on an evaluation of the results recorded to date in the regular monitoring of the environment, it was proved that the mining and processing of uranium ore in the Dolní Rožínka locality does not result into serious pollution or harm to the environment. Local inhabitants differ in their views. It can be caused by unsufficient information supply about mining and processing of uranium ore due to low interest or even concealing in the past.This publication should be used as a source of information for both general public and study purposes.
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Comparsion of the Classical Catheter Angiography and CTAG; the Benefits and Deficiencies of Both Methods, including Radiation Load
BLAHNÍKOVÁ, Kateřina
The title of this Bachelor{\crq}s Thesis is Comparison of the Classical Catheter Angiography and CTAG; the Benefits and Deficiencies of Both Methods, including Radiation Load. I carried out the comparison in the area of positives and negatives of these methods, related risks and mainly in the area of patient radiation load, which is the subject of the research. The first part deals with brief characteristics of anatomy and vascular system physiology, introduction to both methods, including a chapter dedicated to contrast media and a brief description of radiation protection. When defining the benefits, deficiencies and potential risks I came to a conclusion that there cannot be unequivocally recommended just one method, for both methods provide different advantages and therefore the final decision must be made by the doctor. To assess patient radiation load I used data from 1 July 2008 to 30 June 2009 of patients, who underwent an examination of brain blood vessels in České Budějovice Hospital. To carry out the comparison it was necessary to convert the results into an effective dose. In case of CTAG I made the calculation using a literature available coefficient. For classical catheter angiography I used the version 1.5 PCXMC program. Due to a lack of data (e.g. the angle of a primary beam incidence) the calculation made was only approximate. To find out the occurred error I used data of patients examined from 8 March to 23 March 2010. The consequent statistical data assessment showed that the CTAG method represents bigger radiation exposure for human organism than classical catheter angiography, which proved the hypothesis. In connection with the lack of data regarding the carried out classical catheter angiography I would consider keeping a larger amount of data beneficial for potential calculation of an effective dose. All data required for an accurate calculation of an effective dose can currently be obtained only during the examination.
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The activity of crisis management bodies in Týn nad Vltavou at the preparation and realization of the evacuation of Týn nad Vltavou inhabitants due to the radiation accident {--} MU 3 at the Nuclear Power Station Temelín
HLAVÁČ, Roman
In the introduction part I described the characteristics of Týn nad Vltavou and its main threat for the inhabitants, which is the Nuclear Power Station Temelín (NPS Temelín) situated nearby. In the next part I described the integrated rescue system, its units, position and tasks, further the main bodies of crisis management with the emphasis on the crisis management bodies in Týn nad Vltavou and the crisis planning. In detail there is the description of Security Council and above all Crisis Staff activities at the preparation and solution of crisis situation. Further the thesis deals with the accident preparedness, categorisation of workplaces, where radiation activities are carried out, and also special radiation events, their division and measures which are taken at their announcement. This part is followed by the explanation with the description of inner and outer emergency plan of NPS Temelín. I also mention protection measures which are taken in connection with the radiation accident at NPS Temelín. The part also contains their division, description and the way of implementation. Evacuation of inhabitants, the way of its realization, activities and tasks of crisis management bodies are described in detail. The objective of the thesis was to analyse the tasks and to check up the present readiness of crisis management bodies in Týn nad Vltavou at the preparation and realization of evacuation due to the radiation accident in NPS Temelín. Through the medium of sociological research among the inhabitants of Týn nad Vltavou, which was carried out by the form of inquiry sheet, the knowledge of inhabitants on the problems of evacuation at radiation accident in NPS Temelín was proved. The results gained by the research are the part of the thesis and are shown in graphics.
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Protection of persons present at examinations using ionising radiation.
MRÁZEK, Jiří
This bachelor{\crq}s thesis, entitled Protection of persons present at examinations using of ionizing radiation, seeks to summarize particular methods of radiation protection of medical personnel performing activities involving sources of the ionizing radiation. The introductory part highlights the need of the personnel to be acquainted with certain aspects of radiological physics, with effects of ionizing radiation on the human body, with a possibility of its detection, principles of radiation protection, and its optimization. In the following section the thesis points to the legislation in the area of radiation protection. It considers how are the radiation protection and its optimization interpreted at the radio-diagnostic department. Furthermore, it compares specific data resulting from personal monitoring of selected radiological personnel of the Central Military Hospital in Prague with limits of exposure set up by legislation. The data obtained by the monitoring are then sorted and compared using various examination methods. The thesis seeks to prove that compliance with the principles of radiation protection results in values of the individual monitoring of the personnel not exceeding the limits of exposure set up by legislation. Based on particular results it aims to determine how demanding individual examination methods in terms of the personnel{\crq}s radiation exposure are. This thesis should therefore help not only radiological assistants, but also doctors, nurses, and other personnel working with sources of ionizing radiation understand how important are the protection against ionizing radiation and compliance with principles of radiation protection for reduction of the radiation doses received.
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Staff radiation exposure in application of the PET-CT method
BERTOVÁ, Eva
In my Bachelor-of Science work I have studied the issue of the PET-CT method application and its influence on the radiation exposure of nuclear medicine department staff at Faculty Hospital in Lochotín in Plzeň (FN Plzeň-Lochotín). In the opening chapter, the origin and recent developments in the nuclear medicine is reviewed with special focus on the PET history in the world, the physical principles of PET and the first installations of PET and PET-CT in Czech Republic and FN Plzeň-Lochotín. Then the issue of radiation protection is taken up including its history, the recent status including the relevant legal regulations, the basic principles of radiation protection, the physical methods of protection, exposure monitoring programmes and protection against radiation at the PET-CT section of nuclear medicine department of FN Plzeň-Lochotín. The reason why I chose this subject is the high energy radiation associated with PET-CT requiring special measures to ensure staff protection. The target of this work is comparison of the radiation exposure of the nuclear medicine department staff prior to and following introduction of the PET-CT method and verification of the organisation changes and radiation protection measures adopted. In practical part of my work I compared the values of personal dose equivalents Hp (10) detected with the department staff prior to and following the PET-CT method implementation. The values are shown in tables and graphs. The monthly dose equivalent values detected prior to and following the PET-CT equipment installation have been compared using the statistical method of double sample t-test. The conclusions of this study have been used to verify the efficiency of the radiation protection measures adopted at FN Plzeň-Lochotín, and to compare the status of affairs in Plzeň with those in the Nuclear Medicine Clinic of Medical Faculty and Faculty Hospital in Olomouc and at the PET Centre of the Na Homolce hospital in Prague.
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Dose measuring during laboratory works in the workplace of nuclear medicine by the help of personal dozimeters.
RUSINOVÁ, Jana
One of the most important tasks of the radiation protection is to monitor the amount of external radiation in people who are during their working hours exposed to sources of ionizing radiation.To measure the amount of radiation received by the workers a special device is used {--} the dosimeter.At the department of nuclear medicine in the České Budějovice Hospital, B.Němcové 584/54, České Budějovice, thermoluminiscence dosimeters are used in practice for this purpose. In this work, I compared the data obtained by a thermoluminiscence dosimeter and the DMC 2000 XB personal electronic dosimeter made by the Merlin Gerin company. Based on the results of this comparison, it was my task to determine which of the two dosimeters shows more precision and efficiency and therefore would be more suitable for further use in nuclear medicine.
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Confrontation of radiation dose of professional in nuclear medicine department in Hradec Králové before and after installation PET/CT, possibilities of monitoring
JANSOVÁ, Martina
This Bachelor Thesis deals with the radiation load of Nuclear Medicine employees of University Hospital Hradec Králové before and after the introduction of PET/CT examinations. Compared with usual examinations with gamma emitters and therapy with open beta emitters, the PET/CT examination method uses positron emitters and is carried out at the Department of Nuclear Medicine of University Hospital Hradec Králové (DNM UHHK). The use of positron emitters leads to increased demand in respect of radiation protection and work organisation. I made an evaluation of doses from personal dosimetry from 2004 until 2008 prior to the introduction of the PET/CT examination methodology; and year 2009 is subsequently assessed in respect of the situation after the introduction of PET/CT examinations. The results of doses are provided in tables. Film dosimeters and thermoluminescence (TL) ring dosimeters had been used for personal dosimetry until 2008. Digital dosimeters have been also used for personal dosimetry since 2009, and they are further included in the comparison of the received radiation doses of employees. The results were used for an evaluation of optimisation of radiation protection at the DNM UHHK.
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Optimalization radiation protection with by using method "cost-benefit". Calculation for power plant Temelín ČEZ, a.s.
FOLTÝN, Pavel
Currently in the area of radiation protection, the principle ALARA (As Low As Reasonable Achievable) is being used. Through this principle the radiation burden of workers with ionising radiation is optimised. One of the economic tools used here is the {\clqq}cost-benefit analysis``. It is one of the first analytical methods which are recommended by the ICRP (International Commission on Radiological Protection) for optimising costs needed to secure radiation protection. The cost benefit analysis is a good and efficient economical tool. With the help of this method it is possible to do the optimisation as well as to prove it. It takes into consideration all significant economic and social factors that are prescribed and recommended. Especially, it can prove that all expositions are kept as low as they are reasonable achievable, while considering the economic angle. Basically, it is a conception which is applicable in all areas of the public as well as private sector, in all areas of human activity. In this thesis some particular examples of using the CBA at the NPP Temelín are shown and compared with the achieved level of RP. Based on that the ALARA system at our workplace is demonstrated. The CB analysis with its extended forms helps to make principal and continuous decisions, and it is an essential factor in protection from harmful effects of ionising radiation. Its main contribution lies in the areas where it is necessary to build additional technical or building barriers. It is very important in designing and building new workplaces with ionising radiation.
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