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Experimentální studium pole neutronů v podkritickém urychlovačem řízeném jaderném reaktoru
Zeman, Miroslav ; Janda,, Jiří (oponent) ; Chudoba,, Petr (oponent) ; Katovský, Karel (vedoucí práce)
Tato disertační práce se zabývá ozařováním spalační sestavy složené z více než půl tuny přírodního uranu svazkem protonů o energii 660 MeV ve Spojeném ústavu jaderných výzkumů v Dubně. V obou případech byly napříč celou sestavou v horizontálních a vertikálních pozicích rozloženy prahové aktivační detektory (Al-27, Mn-55, Co-59 a In-nat), které byly aktivovány sekundárními neutrony produkovanými spalační reakcí. Aktivované terčíky byly měřeny a následně vyhodnocovány s pomocí jaderné gama-spektrometrie. V prahových detektorech byly analyzovány různé radionuklidy a byly určeny jejich hodnoty reakčních rychlostí. Z vypočítaných reakčních rychlostí byly určeny poměrné hodnoty pro ozařování sestavy obložené olovem a bez tohoto obložení. Následně bylo v jednotlivých pozicích spalační sestavy dopočítáno rozložení neutronového spektra generovaného uvnitř sestavy s využitím Co-59. Experimentálně získaná data byla porovnána se simulacemi provedenými metodou Monte Carlo pomocí kódu MCNPX 2.7.0.
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Monitoring and Simulation of ADS Experimental Target Behaviour, Heat Generation, and Neutron Leakage
Svoboda, Josef ; Kliman,, Ján (oponent) ; Wagner,, Vladimír (oponent) ; Katovský, Karel (vedoucí práce)
Sub-critical Accelerator-Driven Systems (ADS) technology is able to deal spent nuclear fuel of present nuclear reactors, by using the transmutation technique of long-lived radioactive isotopes. As well, the ADS technology is solving the potential problem with the lack of U-235 by possible utilisation of U-238 or abundant Th-232. This doctoral thesis deals with research on the topic of spallation reaction and heat generation of various experimental targets in the frame of base ADS research. All thermal experiments, in total 13, have been performed at Joint Institute for Nuclear Research (JINR) in Dubna, Russian Federation, during the years 2015-2019. Various targets were irradiated as 512 kg of natural uranium target QUINTA, elongated cylindrical lead target and carbon target, or lead bricks target by 660 MeV protons at the irradiation facility Phasotron at JINR. A special experiment was performed with irradiation of two small uranium cylinders the QUINTA consist of. The author investigates the heat generation by proton reactions (inelastic scattering, and ionisation losses) which are part of spallation reaction including Coulomb scattering (or Rutherford scattering, which represents elastic scattering of charged particles); neutron reaction (mostly contributed by fission); pion reaction; and finally gamma heating, the heat generated by photon capturing. The temperature was experimentally measured by highly accurate and specially calibrated thermocouples. The temperature was measured on the surface, and also inside of the target. Additional research was aimed at neutron leakage monitoring T measurement of tiny volume probes by accurate thermocouples. The first probe contains a small amount of fissile material and the second one of non-fissile material with similar material characteristics. Leaking neutrons (neutron flux outside of the target) were detected due to direct heating by fission reactions. This work deals with accurate temperature measurement by thermocouples. It uses the LabView software for data acquisition, the National Instrument hardware for measuring, and Python 3.7. for data manipulation, analysing and visualisation (with employing several libraries). The particle transportation is simulated by MCNPX 2.7.0. and finally, the heat transfer and surface temperature estimation are simulated by ANSYS Fluent (or ANSYS Transient Thermal for simpler problems).
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Monitoring and Simulation of ADS Experimental Target Behaviour, Heat Generation, and Neutron Leakage
Svoboda, Josef ; Kliman,, Ján (oponent) ; Wagner,, Vladimír (oponent) ; Katovský, Karel (vedoucí práce)
Sub-critical Accelerator-Driven Systems (ADS) technology is able to deal spent nuclear fuel of present nuclear reactors, by using the transmutation technique of long-lived radioactive isotopes. As well, the ADS technology is solving the potential problem with the lack of U-235 by possible utilisation of U-238 or abundant Th-232. This doctoral thesis deals with research on the topic of spallation reaction and heat generation of various experimental targets in the frame of base ADS research. All thermal experiments, in total 13, have been performed at Joint Institute for Nuclear Research (JINR) in Dubna, Russian Federation, during the years 2015-2019. Various targets were irradiated as 512 kg of natural uranium target QUINTA, elongated cylindrical lead target and carbon target, or lead bricks target by 660 MeV protons at the irradiation facility Phasotron at JINR. A special experiment was performed with irradiation of two small uranium cylinders the QUINTA consist of. The author investigates the heat generation by proton reactions (inelastic scattering, and ionisation losses) which are part of spallation reaction including Coulomb scattering (or Rutherford scattering, which represents elastic scattering of charged particles); neutron reaction (mostly contributed by fission); pion reaction; and finally gamma heating, the heat generated by photon capturing. The temperature was experimentally measured by highly accurate and specially calibrated thermocouples. The temperature was measured on the surface, and also inside of the target. Additional research was aimed at neutron leakage monitoring T measurement of tiny volume probes by accurate thermocouples. The first probe contains a small amount of fissile material and the second one of non-fissile material with similar material characteristics. Leaking neutrons (neutron flux outside of the target) were detected due to direct heating by fission reactions. This work deals with accurate temperature measurement by thermocouples. It uses the LabView software for data acquisition, the National Instrument hardware for measuring, and Python 3.7. for data manipulation, analysing and visualisation (with employing several libraries). The particle transportation is simulated by MCNPX 2.7.0. and finally, the heat transfer and surface temperature estimation are simulated by ANSYS Fluent (or ANSYS Transient Thermal for simpler problems).
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Experimentální studium pole neutronů v podkritickém urychlovačem řízeném jaderném reaktoru
Zeman, Miroslav ; Janda,, Jiří (oponent) ; Chudoba,, Petr (oponent) ; Katovský, Karel (vedoucí práce)
Tato disertační práce se zabývá ozařováním spalační sestavy složené z více než půl tuny přírodního uranu svazkem protonů o energii 660 MeV ve Spojeném ústavu jaderných výzkumů v Dubně. V obou případech byly napříč celou sestavou v horizontálních a vertikálních pozicích rozloženy prahové aktivační detektory (Al-27, Mn-55, Co-59 a In-nat), které byly aktivovány sekundárními neutrony produkovanými spalační reakcí. Aktivované terčíky byly měřeny a následně vyhodnocovány s pomocí jaderné gama-spektrometrie. V prahových detektorech byly analyzovány různé radionuklidy a byly určeny jejich hodnoty reakčních rychlostí. Z vypočítaných reakčních rychlostí byly určeny poměrné hodnoty pro ozařování sestavy obložené olovem a bez tohoto obložení. Následně bylo v jednotlivých pozicích spalační sestavy dopočítáno rozložení neutronového spektra generovaného uvnitř sestavy s využitím Co-59. Experimentálně získaná data byla porovnána se simulacemi provedenými metodou Monte Carlo pomocí kódu MCNPX 2.7.0.
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