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Nuclear accidents and subsequent measures to protect the population
SVITÁK, Daniel
This bachelor thesis deals with the protection of the population and subsequent measures in the event of a radiation emergency. When comparing the two largest nuclear accidents (Chernobyl and Fukushima), a great similarity was found not only in the implementation of safeguard measures, but also in the errors made by the responsible authorities. By comparing these events, we could answer the question of how the approach to protecting the population differed in the bipolar division of the world from the perspective of the "Eastern", which is represented by the former USSR and the view of the "Western" represented by Japan. With the resulting analysis, we confirmed that in both the USSR and Japan, this approach differed only in the source of the likely risk, which was given greater attention than the other risks. In case of comparison of the measures of protection of the population of the Czech Republic, which are mentioned in the emergency plans, with those introduced in the world in the case of The RMU, we concluded that the measures of the Czech Republic are on the same level and can be considered as a world standard. To support the resulting claims, the measures introduced at the Fukushima RMU are compared with those during the 2015 Zone Temelín emergency exercise. An integral part is the evaluation of the level of information of the Czech population in the field of protection of the population. An analysis of the results of the supplementary questionnaire survey confirmed the claim of low level of information of the inhabitants of the Czech Republic. Therefore, the work will also focus on the need to raise public awareness in the field of population protection and propose measures to raise the level of information to the required level.
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The feasibility of different biodosimetric methods for dose estimation in case of radiation accidents.
PAVEZKA, Luboš
A deterioration of the coincidental hazards linked to the use of ionizing radiation is currently observed for four reasons. First, the increasing demand for radiation sources in numerous industrial applications (food sterilization, construction, engineering) leads to an increasing likelihood of loss of the sources or abnormal/unsuitable use and storage. Second, advances in medicine generate new protocols and tools that are more efficient but also much more complex to execute, increasing the risk of accidental overexposure. Third, the possibility of a terrorist attack using radiological or nuclear devices has to be taken into account. Finally, recent events in Fukushima (Japan) highlight the risks of exposure in the case of nuclear power plant accidents. All these issues could lead to the accidental exposure of one to several thousand individuals not wearing dosimeters. Thus, it is essential to be able to assess the exposure level of victims. Nowadays, this evaluation is based on clinical diagnosis (mainly irradiation symptoms and hematological variations) supplemented with biological dosimetry andphysical dose reconstruction. Biological dosimetry is especially important when the personal dosimeter is lacking or when the accidental context is unclear. All this information should help the medical staff to deliver appropriate medical care and to manage the long-term medical follow-up, if required. To fulfil this task, the dose estimates has to be timely, exact and conclusively reached in large-scale disasters. In my bachelor thesis, I have focused on the applicability of the various techniques for different scenarios: small- and large-scale exposes to different levels of a radiation that could manage to the urgent radiation syndrome and exposures with lower doses that do not need direct care, but should be followed for evidence of long-term impacts. The principle of biodozimetry is to utilize changes caused in the individual by ionizing radiation to estimate the dose and, if feasible, to predict or reflect the clinically relevant reaction. Optimally, the changes should be specific for ionizing radiation, and the response should be unaffected by prior medical or physiological variations among subjects, including changes that might be caused by the stress and trauma from a radiation event. There are two basic types of biodozimetry with dissimilar and very often complementary characteristics: those based on changes in biological parameters such as gene activation or chromosomal abnormalities and those based on physical changes in tissues. Factors advised comprise: time interval when the assay is feasible biologically, time for sample preparation and analysis, dose finding limit, ease of use, logistical demands, potential efficiency, point-of-care eligibility, and the ability to support patient diagnosis and treatment within a therapeutically relevant time point. The development of of biodozimetry has been mainly encouraged by the needs after a large-scale accident, where it is essential to have a tool or device to identify those individuals who would profit to be brought into the medical care system.
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Detection of Ionizing Radiation in Radiological Controlled Area of Nuclear Power Plant Temelín.
DOUDOVÁ, Vendula
The power plant Temelin is equipped with the modern system of radiation control. The system meets high technical standard. It ensures the control of all parameters according requirements of our legislative and government authority. The system provides the control in such dimension to have necessary information about irradiation of workers and the population in neighbourhood, outlets to environment, and about the situation in the some selected technological circuits and systems. It is necessary to monitor the integrity of barriers in every mode of power plant Temelin including emergency and post-emergency conditions. The working environment in contained area of the power plant Temelin is monitored with stationary monitoring system and with the mobile instruments according the approved operational manual. The workplace monitoring is realized with surveillance, measurement, evaluation and recording parameters of ionizing radiation field and the occurrence of radionuclides in working area, especially the dose equivalent on the working area and the volume activities in the environment and the surface activities.
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