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LOCA Energy Performance Study for Simulation of Heavy Accident at NPP
Zemčíková, Kristína ; Andrle,, Karel (referee) ; Mastný, Petr (advisor)
This bachelor’s thesis studies the energy performance of the LOCA device used for the simulation of accidents at nuclear power plants, which can be found at the CV Řež research centre. LOCA stands for Loss of Coolant Accident, which is kind of serious accident that may occur at NPPs. During the accident, the coolant is assumed to be leaking due to a fissure in one of the main pipes. The unique LOCA device at the research centre simulates this accident and is used for testing important components utilised at nuclear power plants. This thesis describes the LOCA device and attempts to determine its energy consumption over the course of a 10-day experiment. By leveraging the consumption curve of the research centre, possible operational optimisations applicable to this LOCA device technology will be proposed.
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Accelerator driven nuclear reactor neutron field parameters determination
Zemčíková, Kristína ; Šťastný, Ondřej (referee) ; Katovský, Karel (advisor)
The master thesis deals with calculation of neutron field parameters in systems controlled by an accelerator called the Accelerator Driven System (ADS). Firstly physical principle is described, along with its parts as well as the history and present of ADS projects worldwide. Subsequently, neutron activation analysis and gamma spectrometry are described in more detail. The experiment on AmBe neutron source and on Microtron MT25 is presented in the experimental part. Lastly, the reaction rates are calculated.
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LOCA Energy Performance Study for Simulation of Heavy Accident at NPP
Zemčíková, Kristína ; Andrle,, Karel (referee) ; Mastný, Petr (advisor)
This bachelor’s thesis studies the energy performance of the LOCA device used for the simulation of accidents at nuclear power plants, which can be found at the CV Řež research centre. LOCA stands for Loss of Coolant Accident, which is kind of serious accident that may occur at NPPs. During the accident, the coolant is assumed to be leaking due to a fissure in one of the main pipes. The unique LOCA device at the research centre simulates this accident and is used for testing important components utilised at nuclear power plants. This thesis describes the LOCA device and attempts to determine its energy consumption over the course of a 10-day experiment. By leveraging the consumption curve of the research centre, possible operational optimisations applicable to this LOCA device technology will be proposed.
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