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Trends in nuclear fuel development
Takács, Gergő ; Števanka, Kamil (referee) ; Foral, Štěpán (advisor)
The aim of the bachelor thesis is to acquaint the reader with the differences between pressurized water reactors of the eastern and western type. It describes the differences in the materials used in the cladding and describes the concepts of individual fuel assemblies. It devotes a section to the various events that occur between the fuel and the cladding during the fission reaction. It also gives an overview of what the largest companies are dealing with, describes future trends in the development of nuclear fuel.
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Design of equipment of spent nuclear fuel assemblies
Šimek, Ondřej ; Rausch, Ivan (referee) ; Vojáčková, Jitka (advisor)
The diploma thesis aim to the design of equipment for ŠKODA JS a.s., which is part of a new inspection stand (N-SIO). This equipment is an inspection column that provides the possibility to inspect spent fuel assemblies at the operation of the Temelín nuclear power plant. This master thesis is also a summary of the whole design of the new inspection stand and a description of the individual inspection components and devices. One of the parts of the thesis is also a basic strength analysis and a drawing of the main assembly of inspection equipment.
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Radiation damage of VVER-440 based Dukovany NPP reactor pressure vessel investigation
Říha, Tomáš ; Martinec, Jiří (referee) ; Šen, Hugo (advisor)
This master‘s thesis deals with radiation damage of reactor pressure vessels, specifically of NPP Dukovany Unit No. 3. In general damage mechanisms of reactor steels are described and possibilities of monitoring of material degradation and its recovery used at NPP’s all over the world are mentioned as well. A practical part of the thesis is focused on interpretation of analyses carried out with the assistance of MOBY DICK code. The ground of these analyses is a neutron fluence value development on different locations of RPV for the whole life of operation up to 24th cycle. The analyses results are put into context with performed in-service inspections. The thesis follows up with neutron fluence computation for the future cycles containing new types of nuclear fuel up to 34th cycle. The outcome of practical part of the master‘s thesis is a comparison between new types of nuclear fuel with respect to radiation damage of RPV’s.
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Nuclear Fuel Cycle of Dukovany NPP
Dudáš, Michal ; Foral, Štěpán (referee) ; Katovský, Karel (advisor)
The goal of this bachelor’s thesis is to introduce the nuclear fuel cycle of nuclear power plant Dukovany focusing on its middle part. It describes the methods of loading fuel assemblies in-out and out-in, the differences between continual (on-load reactors) and campaign kind of fuel cycle. There are briefly described individual types of fuel used on nuclear power plant Dukovany from the start to recent days. It is further followed by the external fuel cycle. The front end describes more about mining, enrichment and fabrication. There are also few different separation methods of uranium described. The back end deals with different ways of spent fuel storage, spent fuel pools, and dry cask storage as well as ultimate disposal. The paper also contains brief overview among the most known nuclear reactors with the short descriptions of its own nuclear fuel cycles. It is further followed by description of fuel cycles with different length, focusing on different types of fuel and different loading methods. There is also a possible concept of outages for nuclear power plant Dukovany considering few different long lasting campaigns. The paper contains economic assessment considering the simplified conditions. It also deals with pros and cons of individual cycles focusing on organization operating and spent fuel storage.
|
|
|
Trends in nuclear fuel development
Takács, Gergő ; Števanka, Kamil (referee) ; Foral, Štěpán (advisor)
The aim of the bachelor thesis is to acquaint the reader with the differences between pressurized water reactors of the eastern and western type. It describes the differences in the materials used in the cladding and describes the concepts of individual fuel assemblies. It devotes a section to the various events that occur between the fuel and the cladding during the fission reaction. It also gives an overview of what the largest companies are dealing with, describes future trends in the development of nuclear fuel.
|
|
|
Design of equipment of spent nuclear fuel assemblies
Šimek, Ondřej ; Rausch, Ivan (referee) ; Vojáčková, Jitka (advisor)
The diploma thesis aim to the design of equipment for ŠKODA JS a.s., which is part of a new inspection stand (N-SIO). This equipment is an inspection column that provides the possibility to inspect spent fuel assemblies at the operation of the Temelín nuclear power plant. This master thesis is also a summary of the whole design of the new inspection stand and a description of the individual inspection components and devices. One of the parts of the thesis is also a basic strength analysis and a drawing of the main assembly of inspection equipment.
|
|
|
Nuclear Fuel Cycle of Dukovany NPP
Dudáš, Michal ; Foral, Štěpán (referee) ; Katovský, Karel (advisor)
The goal of this bachelor’s thesis is to introduce the nuclear fuel cycle of nuclear power plant Dukovany focusing on its middle part. It describes the methods of loading fuel assemblies in-out and out-in, the differences between continual (on-load reactors) and campaign kind of fuel cycle. There are briefly described individual types of fuel used on nuclear power plant Dukovany from the start to recent days. It is further followed by the external fuel cycle. The front end describes more about mining, enrichment and fabrication. There are also few different separation methods of uranium described. The back end deals with different ways of spent fuel storage, spent fuel pools, and dry cask storage as well as ultimate disposal. The paper also contains brief overview among the most known nuclear reactors with the short descriptions of its own nuclear fuel cycles. It is further followed by description of fuel cycles with different length, focusing on different types of fuel and different loading methods. There is also a possible concept of outages for nuclear power plant Dukovany considering few different long lasting campaigns. The paper contains economic assessment considering the simplified conditions. It also deals with pros and cons of individual cycles focusing on organization operating and spent fuel storage.
|
|
|
Radiation damage of VVER-440 based Dukovany NPP reactor pressure vessel investigation
Říha, Tomáš ; Martinec, Jiří (referee) ; Šen, Hugo (advisor)
This master‘s thesis deals with radiation damage of reactor pressure vessels, specifically of NPP Dukovany Unit No. 3. In general damage mechanisms of reactor steels are described and possibilities of monitoring of material degradation and its recovery used at NPP’s all over the world are mentioned as well. A practical part of the thesis is focused on interpretation of analyses carried out with the assistance of MOBY DICK code. The ground of these analyses is a neutron fluence value development on different locations of RPV for the whole life of operation up to 24th cycle. The analyses results are put into context with performed in-service inspections. The thesis follows up with neutron fluence computation for the future cycles containing new types of nuclear fuel up to 34th cycle. The outcome of practical part of the master‘s thesis is a comparison between new types of nuclear fuel with respect to radiation damage of RPV’s.
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