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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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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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Methods of neutron detection
Arbeit, Vít ; Števanka, Kamil (referee) ; Mičian, Peter (advisor)
This bachelor thesis deal with neutrons, ways to detect them and with neutron detectors themselves. The theoretical part includes description of all principles by which it is possible to detect them and defines both already established neutron detectors and the latest type of detector. The practical part is focused on realization of Bonner spheres and the measurement of their properties on a neutron source 241Am-Be.
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Characterization of the neutron AmBe source using threshold activation detectors
Burian, Jiří ; Zeman, Miroslav (referee) ; Král, Dušan (advisor)
Neutron activation analysis is used to characterize an unknown neutron field source or material of unknown composition. Using known reactions that take place in the activation detector due to the action of the neutron field, their measurement and evaluation, we can describe the composition of the source if we know the material composition of the activation detector, or, conversely, if we do not know the materials from which the activation detector is made, we can find out if we put this detector of unknown composition into the action of neutron radiation of known origin.
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Methods of neutron detection
Arbeit, Vít ; Števanka, Kamil (referee) ; Mičian, Peter (advisor)
This bachelor thesis deal with neutrons, ways to detect them and with neutron detectors themselves. The theoretical part includes description of all principles by which it is possible to detect them and defines both already established neutron detectors and the latest type of detector. The practical part is focused on realization of Bonner spheres and the measurement of their properties on a neutron source 241Am-Be.
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|
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Characterization of the neutron AmBe source using threshold activation detectors
Burian, Jiří ; Zeman, Miroslav (referee) ; Král, Dušan (advisor)
Neutron activation analysis is used to characterize an unknown neutron field source or material of unknown composition. Using known reactions that take place in the activation detector due to the action of the neutron field, their measurement and evaluation, we can describe the composition of the source if we know the material composition of the activation detector, or, conversely, if we do not know the materials from which the activation detector is made, we can find out if we put this detector of unknown composition into the action of neutron radiation of known origin.
|
|
|
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.
|
|
|
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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