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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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Determination of nuclear reactions' microscopic cross-sections using an accelerator-driven neutron source
Filová, Vendula ; Šťastný, Ondřej (referee) ; Král, Dušan (advisor)
Tato práce se věnuje určení mikroskopických účinných průřezů interakcí neutronů s indiem. Teoretická část shrnuje neutronové zdroje používané ve vědě i průmyslu, popisuje princip jejich fungování a představuje příklady jejich aplikací. Praktická část obsahuje postup vyhodnocování velikostí účinných průřezů včetně jednotlivých provedených korekcí. Byly vyhodnocována data celkem ze tří experimentů, při kterých byly produkovány neutrony interakcí protonů s tenkým lithiovým terčem. Kvazi monoenergetickým neutronům byly vystaveny sendviče folií včetně foile z india, produkty interakcí byly měřeny pomocí gamma spektrometrie. Výsledné mikroskopické účinné průřezy jsou porovnány s daty z knihoven evaluovaných dat a z knihovny EXFOR.
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Sodium cooled fast reactors
Daňhel, Aleš ; Katovský, Karel (referee) ; Foral, Štěpán (advisor)
This bachelor’s thesis deals with the sodium-cooled fast reactors. It comprehensively describes the problem of sodium-cooled fast reactors. Attention was paid to the basic specifications and parameters of these reactors. There was briefly described nuclear reactions which are under way in core of sodium-cooled fast reactors but also chemical reactions which are linked to function of liquid sodium as a coolant and heat transfer substance. Attention was also paid to the differences in the reactor core configuration and to the machine device specific for sodium-cooled fast reactors. Further on this bachelor’s thesis puts on the overview of sodium-cooled fast reactors that have worked, are still working or are under construction in each country all over the world. There was briefly described generation IV nuclear reactors, particularly its history and reasons that originate generation IV. Under generation IV was also described nuclear reactor SFR and highlighted differences compared to existing sodium-cooled fast reactors. In the practical part of this bachelor’s thesis is easily made a calculation of the heat transfer from the fuel rod to the cooling sodium and there is also mentioned course of the heat transfer coefficient along the fuel rod. This calculation was made by computing program MATLAB.
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Determination of nuclear reactions' microscopic cross-sections using an accelerator-driven neutron source
Filová, Vendula ; Šťastný, Ondřej (referee) ; Král, Dušan (advisor)
Tato práce se věnuje určení mikroskopických účinných průřezů interakcí neutronů s indiem. Teoretická část shrnuje neutronové zdroje používané ve vědě i průmyslu, popisuje princip jejich fungování a představuje příklady jejich aplikací. Praktická část obsahuje postup vyhodnocování velikostí účinných průřezů včetně jednotlivých provedených korekcí. Byly vyhodnocována data celkem ze tří experimentů, při kterých byly produkovány neutrony interakcí protonů s tenkým lithiovým terčem. Kvazi monoenergetickým neutronům byly vystaveny sendviče folií včetně foile z india, produkty interakcí byly měřeny pomocí gamma spektrometrie. Výsledné mikroskopické účinné průřezy jsou porovnány s daty z knihoven evaluovaných dat a z knihovny EXFOR.
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Use of activation detectors for neutron field measurement in models of ADTS
Chudoba, Petr
Accelerator driven transmutation systems could be a solution to the problem with long-lived nuclear waste and opening the way to thorium fuel cycle. Due to intensive neutron source based on spallation reaction are these systems very litle dependent on the arrangement of the core and fuel quality. These systems can transmute the spent fuel, eventually 232Th or 238U without affecting maintenance of fission reaction. Additionally subcritical blanket ensures high safety. For these systems it is necessary to know the cross sections of reactions of fast neutrons produced in the spallation reaction with different materials. This data is necessary not only for the selection of appropriate construction materials, but also for creation of programs simulating accelerator driven transmutation systems. This thesis is focused on the experimental determination of cross sections of reactions 89Y(n,2n)88Y and 89Y(n,3n)87Y with neutron energies from 17,6 to 33,6 MeV. Yttrium is analyzed for its (n,xn) threshold reactions, which makes it appropriet activation detector for study of the neutron fields in model configurations of accelerator driven transmutation systems. The obtained cross sections are unique, in that so far there are no experimental data for used neutron energies. Powered by TCPDF (www.tcpdf.org)
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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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Use of activation detectors for neutron field measurement in models of ADTS
Chudoba, Petr
Accelerator driven transmutation systems could be a solution to the problem with long-lived nuclear waste and opening the way to thorium fuel cycle. Due to intensive neutron source based on spallation reaction are these systems very litle dependent on the arrangement of the core and fuel quality. These systems can transmute the spent fuel, eventually 232Th or 238U without affecting maintenance of fission reaction. Additionally subcritical blanket ensures high safety. For these systems it is necessary to know the cross sections of reactions of fast neutrons produced in the spallation reaction with different materials. This data is necessary not only for the selection of appropriate construction materials, but also for creation of programs simulating accelerator driven transmutation systems. This thesis is focused on the experimental determination of cross sections of reactions 89Y(n,2n)88Y and 89Y(n,3n)87Y with neutron energies from 17,6 to 33,6 MeV. Yttrium is analyzed for its (n,xn) threshold reactions, which makes it appropriet activation detector for study of the neutron fields in model configurations of accelerator driven transmutation systems. The obtained cross sections are unique, in that so far there are no experimental data for used neutron energies. Powered by TCPDF (www.tcpdf.org)
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Use of activation detectors for neutron field measurement in models of ADTS
Chudoba, Petr ; Wagner, Vladimír (advisor) ; Krtička, Milan (referee)
Accelerator driven transmutation systems could be a solution to the problem with long-lived nuclear waste and opening the way to thorium fuel cycle. Due to intensive neutron source based on spallation reaction are these systems very litle dependent on the arrangement of the core and fuel quality. These systems can transmute the spent fuel, eventually 232Th or 238U without affecting maintenance of fission reaction. Additionally subcritical blanket ensures high safety. For these systems it is necessary to know the cross sections of reactions of fast neutrons produced in the spallation reaction with different materials. This data is necessary not only for the selection of appropriate construction materials, but also for creation of programs simulating accelerator driven transmutation systems. This thesis is focused on the experimental determination of cross sections of reactions 89Y(n,2n)88Y and 89Y(n,3n)87Y with neutron energies from 17,6 to 33,6 MeV. Yttrium is analyzed for its (n,xn) threshold reactions, which makes it appropriet activation detector for study of the neutron fields in model configurations of accelerator driven transmutation systems. The obtained cross sections are unique, in that so far there are no experimental data for used neutron energies.
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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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