The main object of this work is the technology of radio frequency controlled inductively coupled plasma, abbreviated RF-ICP. The specific goal of the work was the application of surface layers of tungsten and analysis of the influence of changes in process conditions on the resulting microstructure and chemical composition of deposited coatings. The monitored conditions were torch power, choice of carrier gas, powder feedrate.

The main aim of this diploma thesis is to acquaint the reader by the means of research with heat diagrams of nuclear power plants, and subsequently, submit a scheme design of partial components and their involvement to heat diagram. The work also reflects different drive variations of circulation pumps and cooling circuits.

The Master Thesis deals with the use of thorium nuclear fuel in accelerator driven systems. Basic principle of ADS, present situation and future possibilities are described in this work. The main goal of the work is determination of neutron flux in spallation target QUINTA. In December 2013, an experiment was performed at Joint Institute for Nuclear Research, Dubna. Samples of cobalt, situated at different positions in QUINTA target, were irradiated in secondary neutron field generated by deuteron beam of energies 2 AGeV and 4 AGeV and beam of C-12 with energy 2 AGeV. The samples were measured with the use of germanium semiconductor detectors and analysed using gamma-ray spectrometry. Reaction rates of Co-59 products were determined. Neutron flux was determined in setup QUINTA on the base of experimental reaction rates. Experimental reaction rates were compared with calcula1tion of MCNPX code.

Viscous dampers are widely used to ensure seismic resistance of pipelines and equipment in nuclear power plants. Damping characteristics of these dampers are nonlinearly frequency dependent and thus causing complications in computational modelling of seismic response. Engineers commonly use two ways to deal with this nonlinearity: The first option is to consider damper by means of “snubber”. This is essentially linear spring element that is active for dynamic load and does not resist static loads. Snubber behaviour during seismic event is described by a equivalent stiffness (sometimes called pseudostiffness). The equivalent stiffness could be defined by the iterative calculations of piping natural frequencies and mode shapes taking into account seismic excitation. However, in complicated structures such as the main circulation loop of nuclear power plant the iterative calculation is difficult and could bring significant inaccuracies. On the other hand, the benefit of such modelling is a possibility to apply the commonly used linear response spectrum method for a solution. The second option is to describe damping characteristics using suitable rheological model. The seismic response is than determined by direct integration of the equations of motion. The behaviour of dampers is described exactly enough but the calculation and post-processing, especially nodal stresses time-histories, are time consuming. The goal of this work was to find a methodology for determining the seismic response of complex pipe systems with viscous dampers. Methodology allows a sufficiently accurate determination of the seismic response of piping systems and also allows obtaining of the results in effective time. The procedure is as follows. Firstly, specialized piping program (AutoPIPE) is used for the development of computational model. Next step is to determine a static response of structure and its verification with experimental measurements, if possible. Using script in Python language a computational model is converted from AutoPIPE into general finite element model in ANSYS system. Four-parameter Maxwell rheological model is used to describe behaviour of viscous dampers. Seismic load is represented by synthetic accelerograms. Newmark algorithm of direct integration of the equation of motion is used to obtain seismic response (only reactions and displacements in nodes of interest are necessary). Than is the equivalent stiffness is than gained from displacements and reactions as median value of their ratios. Received stiffness are subsequently transferred to AutoPIPE program where the seismic solution is performed using response spectra method. Finally, the dynamic response is combined with the static response and stress assessment according standards is done. The created methodology was applied in the seismic resistance calculation of the main circulation piping and piping of pressurizer in nuclear power plants type VVER 440 and type VVER 1000.

Nuclear Security research is an established subdiscipline in security studies. According to some authors is this field of research currently split into two groups of scientists - the "political scientists" and "historians" - who employ widely different approaches to research of the subject and communicate with each other on a minimal basis. This master thesis uses tools of bibliometric citational analysis to validate the existence of this gap on the level of academic citations. The author analyses this phenomenon on the dataset based on the data from the database Scopus. Results of the research bring new insights into the citational structure of set subdiscipline, which shows that the presumed gap between two supposedly not communicating groups does not appear on the level citations.

Diploma thesis is focused on comparison of small punch test results and tensile test results. For experiments were chosen steel P91, 10Ch2MFA, 20CrNi2MoV, 11 416 and 42 2707. These steel are used in nuclear power engineering, or they were developed for this purpose. Basic mechanical characteristics, namely ultimate tensile stress and yield stress, were evaluated from small punch test records of observed materials. This is done via convenient correlation relationships. Obtained values were compared with values obtained by conventional tensile tests. There are mentioned own suggested correlation relationships and comparison of temperature curves gained from small punch test and tensile test in the thesis. Assessment of microstructure of observed materials and analysis of fracture surfaces was provided as well. It was found out, that for assessing basic mechanical characteristics (ultimate tensile stress and yield stress) is the best to suggest own correlation relationships, instead of using universal relationships from literature. The fracture mechanism of all types of assessed steel was ductile in entire temperature range (up to -40 °C).

CHARLES UNIVERSITY FACULTY OF SOCIAL SCIENCES Institute of Political Studies Department of security studies Nuclear Security Studies Scholarship: A Social Network Analysis Master's thesis Author: Kryštof Kučmáš Study programme: Security Studies Supervisor: PhDr. Michal Smetana, Ph.D. Year of the defence: 2020 Declaration 1. I hereby declare that I have compiled this thesis using the listed literature and resources only. 2. I hereby declare that my thesis has not been used to gain any other academic title. 3. I fully agree to my work being used for study and scientific purposes. In Prague on 5. 1. Kryštof Kučmáš References KUČMÁŠ, Kryštof. Nuclear Security Studies Scholarship: A Social Network Analysis. Praha, 2020. Master's thesis (Mgr.) Charles University, Faculty of Social Sciences, Institute of Political Science. Department of Security Studies. Supervisor PhDr. Michal Smetana, Ph.D. Length of the thesis: 46382 char Abstract The nuclear security scholarship is as influential as varied. The thesis Nuclear Security Studies Scholarship: A Social Network Analysis tries to provide a different angle of literature analysis. Author compiled a high amount of citational data in the field of nuclear security studies and then analyzed it with the tools provided by Social Network Analysis and Citational Analysis....

89 Abstract The topic of the thesis concerns Czech nuclear law. Nuclear law can be defined as a set of special legal norms adjusting the terms of the nuclear energy and ionizing radiation usage, protection of population and environment against ionizing radiation, radiation accidents solving and treatment of radioactive waste. As such, nuclear law fully adjust the behaviour of all the natural and legal persons who are concerned with activities connected to the nuclear materials, ionizing radiation and natural resources of ionizing radiation. The field of nuclear law is closely connected to the branches of science dealing with the nuclear energy and ionizing radiation usage; therefore, the factual issues of which at least the fundamental knowledge is necessary for the understanding of nuclear law are given space at the beginning of the thesis. In its provisions, Czech nuclear law adjustment also reflect a number of international treaties and European Union regulations. On account of this, the next part of the thesis deals briefly with the international and European nuclear law adjustment. Important international organizations of the field are mentioned as well. The core of the paper consists in the part concerning the outline and analysis of the present adjustment of Czech nuclear law. The taxonomy of this...

Active Particles at the Temelin NPP, Radiobiological Risks and Protective Precautions The term active particle (AC) was applied on Temelín NPP (ETE) in order to denominate small fragments of high radioactive matters, sized up to 1 millimeter, forming into primary circuit. In accordance with latest available know-how, the ACs major contains corrosion products, that were activated during passing through reactor core. After primary circuit opening, due to carry out outage works, the ACs will spread into ETE radiation controlled area. In proportion to their size, the ACs activity is relative high, so that the ACs can jeopard workers, who will contact them. This jeopardy is namely associated with AC penetration into organism - ingestion or inhalation. The main goal of this dissertation is to determine grounds of ACs occurence in Temelín NPP, to review ACs radiobiological risks and to evaluate procedures and protective aids, used for assurance of workers radiation protection. This dissertation is resuming actual know-how about ACs occured and occuring in Temelín NPP, including suggestions for radiation protection procedures and for protective aids utilization, that are to be used for reduction of above mentioned jeopardy. Next areas are concerned: - analysis of ACs forming and matters composition - description of ACs physical-radiation parameters - identification of main ACs sources in primary circuit - assesment and evaluation of radiobiological jeopardies, associated with ACs occurence in Temelín NPP radiation controlled area - assesment of procedures and protective aids used for protection of workers, who can be endangered by ACs

The thesis deals with the solution to evacuation of the population from the zone of emergency planning of the nuclear power station Temelín in the event of an incident connected with the release of radioactive substances . It analyzes the way of evacuation of the persons, as one of the most important safety measures to ensure protection of the population. In particular, the work focuses on the correct procedures in the case of realization of the evacuation and competence of the persons involved in safety measures. It lists the basic criteria which are applied in protection of the population from the effects of ionizing radiation in vicinity of nuclear power plants. It proposes improving of quality of security protection and information of persons in the zone of emergency planning. The work is based on valid law regulations and special publications of the examined problems. The predominantly part is based on the laws in force, and expertise of publications covering the evacuation of the area.It refers to the external emergency plan, as the basic document for the planning of measures for the disposal of the consequences of radiation accidents or radiation accidents and the limitation of their consequences for the zone of emergency planning. The theoretical part proceeeds from analysis of contemporary legislation concerning the stated problematics, presents the general characteristics of a nuclear device and zone of emergency planning, defining the basic concepts and discusses the important measures in addressing emergencies arising in connection with radiation accidents in nuclear power plant. The work puts emphasis on the principle of correct behaviour of the population in the event of such an accident. For the processing of the thesis there has been used an exploration method, which is based on the proposed methodology. On the base of analysis of survey, possible ways of improvement of this branch were suggested. From the collected data there have been assessed possible system measures of evacuation with regard to their application in practice.