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Temperature measurement in reactor VVER 440
Virgl, Martin ; Katovský, Karel (referee) ; Povalač, Aleš (advisor)
The main goal of this work is to get acquainted with the issues of temperature measurement and signal digitization in the theoretical level and temperature measurement in the VVER 440 reactor and on inseparable parts of the main circulation loops of the Dukovany Nuclear Power Plant and signal processing of temperature sensors. The measurement of temperatures in the power plant reactor is focused mainly on the used temperature sensors, A / D converters and a description of the systems processing these outputs. Furthermore, the work analyzes the data obtained during the calibration of temperature sensors in the isothermal state and the measurement of the resistance thermometer and thermocouple in laboratory conditions.
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Power and Temperature Distribution in Nuclear Fuel Assemblies of VVER-440 reactor at Dukovany NPP
Smola, Luděk ; Novotný, Filip (referee) ; Katovský, Karel (advisor)
This Master’s thesis focuses on calculation of power and temperature distribution in fuel assemblies of VVER-440 reactor at Dukovany Nuclear Power Plant. Theoretical section contains a brief description of VVER-440 technology, fuel and its development at Dukovany Nuclear Power Plant, basics of heat generation in nuclear reactors as well as an overview and categorization of computer codes, used for core calculations. Of these codes, the MOBY-DICK computer code is then described in depth, including its input and output files. The MOBY-DICK code is later on used for pinwise calculating power distribution of selected fuel cycles of defined units at Dukovany Nuclear Power Plant, with vizualization of output values for characteristic fuel assemblies. Results of this computation are then used for analysis, whether uneven power distribution in the core and heat generation gradient within fuel assemblies have any influence on measuring channel output temperatures, which is the pivotal part of this thesis.
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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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Computation analysis of the VVER-440 nuclear power reactor core
Máca, Pavel ; Šnajdárek, Ladislav (referee) ; Katovský, Karel (advisor)
This thesis is focused on effect of fuel assembly rotation on the reactor core optimization in VVER-440 reactor. In the first part of this thesis, a brief description and main parameters of VVER-440 reactor are introduced. Next chapter is focused on the Dukovany NPP reactor core design, where these reactors are in operation, together with evolution of used fuel assemblies and reactor core design optimization. The practical part of this thesis includes a comparison of reactor core design optimization with and without fuel assemblies‘ rotation. Furthermore, a so-called multiple rotation method is investigated, which could be more suitable compared to the currently used one.
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Temperature measurement in reactor VVER 440
Virgl, Martin ; Katovský, Karel (referee) ; Povalač, Aleš (advisor)
The main goal of this work is to get acquainted with the issues of temperature measurement and signal digitization in the theoretical level and temperature measurement in the VVER 440 reactor and on inseparable parts of the main circulation loops of the Dukovany Nuclear Power Plant and signal processing of temperature sensors. The measurement of temperatures in the power plant reactor is focused mainly on the used temperature sensors, A / D converters and a description of the systems processing these outputs. Furthermore, the work analyzes the data obtained during the calibration of temperature sensors in the isothermal state and the measurement of the resistance thermometer and thermocouple in laboratory conditions.
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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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Power and Temperature Distribution in Nuclear Fuel Assemblies of VVER-440 reactor at Dukovany NPP
Smola, Luděk ; Novotný, Filip (referee) ; Katovský, Karel (advisor)
This Master’s thesis focuses on calculation of power and temperature distribution in fuel assemblies of VVER-440 reactor at Dukovany Nuclear Power Plant. Theoretical section contains a brief description of VVER-440 technology, fuel and its development at Dukovany Nuclear Power Plant, basics of heat generation in nuclear reactors as well as an overview and categorization of computer codes, used for core calculations. Of these codes, the MOBY-DICK computer code is then described in depth, including its input and output files. The MOBY-DICK code is later on used for pinwise calculating power distribution of selected fuel cycles of defined units at Dukovany Nuclear Power Plant, with vizualization of output values for characteristic fuel assemblies. Results of this computation are then used for analysis, whether uneven power distribution in the core and heat generation gradient within fuel assemblies have any influence on measuring channel output temperatures, which is the pivotal part of this thesis.
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