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Ionizing Radiation, Residual Heat Generation, and Inventory of Spent Nuclear Fuel
Hájková, Barbora ; Šťastný, Ondřej (referee) ; Katovský, Karel (advisor)
This bachelor's thesis deals with ionizing radiation, residual heat generation, and inventory of spent nuclear fuel. It introduces types of ionizing radiation and half-life of isotopes, which are contained in the nuclear fuel. Furthermore, using code UwB1, a simulation of the burning of nuclear fuel used at the Dukovany Nuclear Power Plant from the introduction of fuel into the reactor to its storage in deep repositories in 2065, is carried out.
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Comprehensive geological characterization of URF Bukov – part II Geotechnical characterization.
Souček, Kamil ; Vavro, Martin ; Staš, Lubomír ; Kaláb, Zdeněk ; Koníček, Petr ; Georgiovská, Lucie ; Kaláb, Tomáš ; Konečný, Pavel ; Kolcun, Alexej ; Králová, Lucie ; Kubina, Lukáš ; Lednická, Markéta ; Malík, Josef ; Martinec, Petr ; Ptáček, Jiří ; Vavro, Leona ; Waclawik, Petr ; Zajícová, Vendula
This final report was processed as a part of Radioactive Waste Repository Authority project Research support for safety evaluation of the deep repository, which is a part of the preparation for the deep repository of nuclear waste (further DR). The aims of the project were collection and interpretation of geological data, the creation of models and obtaining information necessary for evaluation of potential sites for DR emplacement regarding long-term safety. On the basis of public submitting act, a 4-year contract was signed with ÚJV Řež, a.s. and its subcontractors: Czech Geological Survey, Czech Technical University in Prague, Technical University in Liberec, Institute of Geonics of Czech Academy of Sciences, and companies Arcadis CZ, Progeo, Chemcomex Praha and Centre for Research Řež about providing research support for evaluation of long-term safety.
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Population's Awareness in Issues Associated with Nuclear Waste Repository
HÁKOVÁ, Veronika
The diploma thesis was elaborated on the topic of public awareness on issues related to the nuclear waste repository. The issue of nuclear waste management is currently being updated and increasingly discussed. Especially in connection with the search for a new site for the construction of a deep repository of nuclear waste and spent nuclear fuel. The aim of the thesis was to determine the level of knowledge of the population in the field of nuclear waste, its management, knowledge of the current nuclear waste repositories and the intended deep repository of nuclear waste and spent nuclear fuel and, last but not least, of ionizing radiation. The other task was to compare the level of knowledge of the inhabitants living in one of the sites of the intended underground repository (the Čihadlo site) and the inhabitants living outside this site. The following hypotheses have been established: "The level of knowledge on issues related to the repository for nuclear waste and spent nuclear fuel will be statistically significantly higher for residents living in the Čihadlo site than for those living outside that site" and "Knowledge on issues related to the nuclear waste repository and of spent nuclear fuel will reach at least 70% in both groups." A questionnaire survey was conducted to achieve the objectives set and verify the hypotheses. The results were evaluated using descriptive and mathematical statistics. The questionnaire consisted of 20 questions and 100 respondents from each site. The hypothesis has been confirmed that the level of knowledge of the inhabitants living in the Čihadlo site is statistically significantly higher. Knowledge on issues related to the repository for nuclear waste and spent nuclear fuel reached at least 70% for all respondents only on some issues. In the diploma thesis, there was a picture of the level of knowledge of the inhabitants about nuclear waste, its handling and storage of nuclear waste. The results obtained could be used as one of the bases in the site selection process for building a deep repository.
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The Dukovany NPP spent nuclear fuel source term investigation for deep repository needs according to LTO options
Penzinger, Pavel ; ČEZ,, Ondřej Zlámal, (referee) ; Katovský, Karel (advisor)
The master's thesis deals with the analysis of source term of the spent nuclear fuel of the Dukovany Nuclear Power Plant in order to determine the proposals for the transfer of spent nuclear fuel to a deep geological repository in the Czech Republic. To introduce the reader into the issue are briefly described the main aspects, such as the development of the nuclear fuel used in the history of the Dukovany Nuclear Power Plant. These aspects have an influence on the final draft of the timetable. One of the important partial tasks is the processing of an estimate of the future range of spent nuclear fuel, which is based on the current ideas of company ČEZ, a.s. for the future direction of the fuel cycle at the Dukovany nuclear power plant. For the purposes of this work, the key data are the time dependencies of radioactivity and the development of residual heat in individual fuel assemblies. This data are calculated by the software called PAL440_R4, based on the prepared estimates of the spent nuclear fuel assortment. The calculated data are then edited and sorted by MS Excel. For the sake of completeness, the characteristic values and the time dependencies of the radioactivity and the development of residual heat in fuel assemblies. Final timetables for the transfer of spent nuclear fuel to a deep geological repository are processed in several variants, and their selection and application options are justified. For illustration are important parameters given in the form of tables and charts.
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Safety of the fuel stored in water pool
Mičian, Peter ; Novotný, Filip (referee) ; Foral, Štěpán (advisor)
This diploma thesis deals with storing the spent nuclear fuel and reviewing its safety. The theoretical part analyzes the processes taking place while the fuel is being used, such as fission, isotopic changes, fission gas release, cracking, swelling and densification of fuel pellet. The thesis is also focused on handling the spent fuel and on the way it makes from the reactor, through the spent fuel pool, the transportation, various kinds of storing, till the reprocessing and final deep geological repository. Furthermore, this part of the thesis briefly discusses computing code MCNP, its main characteristics, input files and using. The practical part of the work is focused on creating the model of the spent fuel pool located next to the nuclear reactor WWER 440/V213. This type was chosen, because it is the most used type of nuclear reactor in Czech Republic and Slovakia. With the help of the code MCNP, the multiplication factor of the main configurations of the fuel in the pool was calculated, and then the required safety regulations to ensure sufficient subcriticality, so its safety, were checked. Next, several analysis were performed using this model. These analyses were concerning the temperature of coolant, fuel and the use of various nuclear data libraries. In the future this model can be used to realize new analyses with new kinds of fuels, materials and data libraries.
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Assessing the suitability of a site for the location of a deep repository of spent nuclear fuel and high-level waste in terms of long-term security - Čihadlo candidate site
Havlová, V. ; Bukovská, Z. ; Dudíková Schulmannová, B. ; Dudková, A. ; Franěk, J. ; Holeček, J. ; Hroch, T. ; Jelének, T. ; Jelínek, J. ; Kachlíková, J. ; Kaláb, Zdeněk ; Klomínský, J. ; Kučera, R. ; Kunceová, E. ; Polák, M. ; Uhlík, J. ; Milický, M. ; Nývlt, D. ; Ondra, P. ; Pertoldová, J. ; Rapprich, V. ; Rukavičková, L. ; Šír, P. ; Štědrá, V. ; Švagera, O. ; Verner, K. ; Maryška, J. ; Říha, J. ; Královcová, J. ; Červinka, R. ; Gondolli, J. ; Klajmon, M. ; Kolomá, K. ; Černý, M. ; Vavro, Martin ; Vopálka, D. ; Svoboda, J. ; Vašíček, R. ; Hokr, M. ; Steinová, J. ; Zeman, J. ; Kouřil, M.
This report summarises outline of a report for evaluation of suitability of sites for emplacement o a deep geological repository on the basis of archive information and geological survey conducted from surface.
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Nuclear waste deep repositories in the law
Kasl, Jakub ; Humlíčková, Petra (advisor) ; Žákovská, Karolina (referee)
The thesis deals with nuclear waste deep repositories in the law. With exception of long- term storage the nuclear waste deep repositories represent the only technical solution currently available to deal with the increasing volume of highly radioactive waste and spent nuclear fuel. The planning and construction of nuclear waste deep repository entails number of problems and challenges, both from technical and legal perspectives. The thesis aims to describe current legislation regarding the management of radioactive waste and spent nuclear fuel within the territory of the Czech Republic with a particular focus on planning and construction of a nuclear waste deep repository. There is step by step described procedure of planning and constructing a nuclear waste deep repository under the current legislation. Within this description the author evaluates the current legislation and identifies its major issues. Subsequently, the author reflects on the cause of these issues and proposes their solutions.
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Spent nuclear fuel and its properties
Jestřáb, Tomáš ; Řež,, Martina Malá, Centrum výzkumu (referee) ; Katovský, Karel (advisor)
The main goal of this Bachelor’s thesis is to develop fuel depletion models of a nuclear fuel used at Nuclear Power Plant Dukovany – originally designed nonprofiled fuel used in a three-year cycle, inovated profiled fuel used in a four-year cycle and currently used fuel Gd-2M+ used in a five year fuel cycle. Models are created by computational code UWB1 providing fast calculation of nuclear fuel depletion. Outputs of these models are in thesis graphically displayed and analyzed from the point of view of fuel depletion, enrichment or irradiation time spent in reactor core. These analyses are based on theory including information about the nuclear fuel cycle focusing on its middle part and the back end of the nuclear fuel cycle.
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Spent fuel storage casks thermal and physical properties investigation
Hlatký, Pavel ; Martinec, Jiří (referee) ; Šen, Hugo (advisor)
This work deals with questions of spent fuel storage casks thermal and physical properties investigation. Foundations of mathematics which are necessary for describing field of temperature are included. The work itself contains calculation methods which are split into two parts. The first one deals with simplified analytic solution and the second part solves the whole problem by the numerical computation.
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