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Experimental analysis focused on the effect of chloride salt on neutron flux with different energy levels
Slančík, Tomáš ; Števanka, Kamil (referee) ; Katovský, Karel (advisor)
Master’s thesis focuses on the history and current progress in research of molten salt reactors around the world, with an emphasis placed on the properties of molten salts and the problems associated with their use. In relation to the practical part, one chapter is devoted to the creation of input file in the MCNP software. The practical part deals with neutron activation analysis of graphite prism experiment, which is filled with powder NaCl salt. This experiment is focused on the effect of salt on neutron flux with different energy levels. The whole problem was also simulated in the MCNP environment along with the experiment. At the end of the thesis, the individual methods are compared and evaluated.
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Depletion calculation of VVER 1000 reactor fuel using KENO code
Janošek, Radek ; Katovský, Karel (referee) ; Novotný, Filip (advisor)
The introduction to operational nuclear reactors focusing on light-water pressurized reactor VVER 1000 is in the beginning of this Master´s thesis. This thesis covers basic technology of VVER 1000 reactor with focus on reactor core and nuclear fuel TVSA-T. A significant part of the thesis deal with basic concepts of nuclear safety and its methods. The main goal is to create a model of VVER 1000 reactor, which can be used in nuclear burn-up calculations using KENO code. Therefore a part of this thesis deals with explanation of statistical Monte Carlo method and the KENO code.
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Reseach of Molten Salt Cooled Nuclear Reactor Behavior
Kostečka, Jan ; Števanka, Kamil (referee) ; Katovský, Karel (advisor)
The master ‘s thesis deals with the studying behavior of nuclear reactors cooled by liquid salts and with application of liquid salts for IV. Generation of nuclear reactors. For the use of liquid salts, it’s necessary to change the concept of the structure of nuclear reactors. There are new ways to use new fuel in a liquid state. Each salt compound or a set thereof is original in its nature. Therefore, it is necessary to consider a suitable compound for the purposes employed. These points are discussed in the theoretical part. The thesis examines particularly chloride salts, with which there is not much experience. The practical part monitors and verifies the nuclear properties of chloride salts, in our case it is a solid-state chloride sodium chloride’s compound. In addition to the experimental measurement, the MCNP simulation program is used also.
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Description and Utilization of Small and Medium Sized Nuclear Reactors
Novotný, Filip ; Sklenka,, Ľubomír (referee) ; Katovský, Karel (advisor)
This Bachelor’s thesis examines the area of small- and medium-sized nuclear reactors and their roles in the early development of nuclear energy. The work covers current small- and medium-sized reactors in operation and considers future developments in this area. Included is an analysis of the possibilities for their use and applications in various areas of human activity. The work focuses on new projects of small- and medium-sized reactors, especially on projects considered for the near future. They are evaluated for nuclear weapons proliferation resistance, as well as their economic and technical advantages. Furthermore, an analysis was carried out of the possible uses of small reactors in propulsion of spaceships, and their use in various geographic areas. Knowledge acquired from this analysis applies to the situation in the Czech Republic. Both unrealized projects, and projects which may be realized in the future, have been described.
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Simulation of Accelerator Driven Nuclear Reactor for Spent Nuclear Fuel Transmutation
Jarchovský, Petr ; Ing. Antonín Krása, Ph.D., SCK.CEN Mol (referee) ; Katovský, Karel (advisor)
This master’s thesis deals with usage of burn-up (spent) nuclear fuel in nuclear power plants of next generation – accelerator driven transmutation plants which is produced in current nuclear power plants. This system could significantly reduce the volume of dangerous long-lived radioisotopes and moreover they would be able to take advantage of its great energy potential due to fast neutron spectrum. In the introduction are listed basic knowledge and aspects of spent nuclear fuel along with its reprocessing and the possibility of further use while minimizing environmental impact. As another point detailed description of accelerator driven systems is described together with its basic components. In addition this search is followed by individual chronological enumeration of projects of global significance concerning their current development. Emphasis is placed on SAD and MYRRHA projects, which are used like base for calculations. This last, computational part, deals with the creation of the geometry of subcritical transmutation reactor driven by accelerator and subsequent evaluation which assembly is the most effective for transmutation and energy purposes along with changing of target, nuclear fuel and coolant/moderator.
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Subchannel analysis of VVER-100 reactor core
Bednář, Michal ; Petrosyan, Taron (referee) ; Katovský, Karel (advisor)
This master’s thesis deals with boiling crisis and with departure from nucleate boiling ratio. This thesis explains terms like the boiling crisis in nuclear reactors and the thesis deals with individual parameters of the reactor core, which have an impact on departure from nucleate boiling ratio. After that, the thesis deals with subchannel analysis and describes basic mathematical and physical models of the chosen subchannel program. The thesis then processes, with the ALTHAMC12 subchannel program, the chosen parameters and their impact on departure from nucleate boiling ratio. The conclusion of the diploma thesis deals with the evaluation of the best and worst calculated combination.
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The AmBe Laboratory Neutron Source Field Determination Using Experimental Stend
Jelínek, Martin ; Šťastný, Ondřej (referee) ; Katovský, Karel (advisor)
This master’s thesis provides a comprehensive overview of the conventional neutron sources from the perspective of reactions which lead to the production of neutrons, advantages, disadvantages, properties and their possible utilization. In the relation to the assembly of the laboratory neutron source and the unique experimental stand “Candle” basic methods of the neutron field analysis are outlined and two of them, the neutron activation analysis and the calculation using the MCNP software code are discussed in depth to apply and compare these methods. The experimental part deals with the realization of neutron activation analysis from its design itself, through gamma spectrometry to the cadmium ratio calculation. In compliance with the measurements, a calculation with MCNP code was run and both methods were evaluated and compared. The computation is complemented with the analysis of radiation situation on the borders of the supervised area, which is compared to the legal limit.
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Alternative sources of nuclear energy
Svoboda, Josef ; Zlámal, Ondřej (referee) ; Katovský, Karel (advisor)
In places where it is not possible to use conventional production and distribution of energy, autonomous sources take over. Most of autonomous sources use solar energy, wind energy and other renewable resources. For applications such as special missions into outer space the usage of conventional sources is not possible. Except for powering special satellites, unconventional nuclear sources are also used in autonomous unmanned objects located in distanced areas with extreme natural conditions. It is also used in unusual propulsions of ground, water and air machine. These vehicles are for example pacemaker powered by radioisotope source, submarines, aircrafts and other vehicles supplied by nuclear reactor of unconventional conception. In this bachelor thesis there are globally summarized questions connected with unconventional sources of nuclear energy with detailed description of chosen parts. This work is concerned with finding more efficient machinery for conversion of heat energy supplied by radioisotope decay to electric energy.
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Nuclear reactors for new units in the Czech Republic
Brunčiaková, Miriama ; Martinec, Jiří (referee) ; Katovský, Karel (advisor)
This bachelor thesis is concerned with nuclear reactors in operation, in construction and in project plans. Because of that it is a very actual theme. Czech Republic tries to solve the question about building two new reactors for Temelín-3,4. There are two competitors in this tender. First of them is the CzechRussian consortium MIR.1200 with the alike named project MIR.1200, and the second one is Westinghouse company with the project AP 1000. Both of these projects belong to III.+ generation of nuclear reactors. In comparison with the previous generations, this generation brings evolution changes and uses much more passive security elements. The project AP 1000 solves heavy accidents by passive security systems solely. The project MIR.1200 uses combination of both active and passive security systems.
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Investigation of Ionizing Radiation Infuence to the Communication Systems of Satellites
Golubev, Martin ; Hobst, Leonard (referee) ; Katovský, Karel (advisor)
This master thesis discuss about ionizing radiation, interaction with matter and effects on her. In the work is discussed differend types of interactions of directly ionizing radiation and indirectly ionizing radiation. Below is an overview of methods of shielding from all of types of ionizing radiation. Second part of this thesis discuss about single event effects in semiconductors which are cause by ionizing radiation. At the end is described design of measuring instrument included FPGA chips. This design is discused both from point of wiew hardware and software too.
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