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Provisions for mitigation of consequences in case of major accidents in GFR nuclear reactors
Mlčúch, Adam ; Suk, Ladislav (referee) ; Martinec, Jiří (advisor)
This thesis deals with the severe accident of the gas-cooled fast reactor GFR. At the beginning of the study there is a review of the gas-cooled fast reactor subject. Next part is focused on description of possible solutions for severe accidents with emphasis on the solution applied in the Generation III+ reactors. Chapters that deal with material and thermal balance with severe accident of GFR demonstration unit, along with the chapter which analyses features of the corium, create a basis for the conceptual design of core catcher of GFR demonstration unit, which forms the final part of this thesis.
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Thermal and creep analysis of VVER-1000 reactor pressure vessel at high temperatures caused by fuel melting during severe accident
Gabriel, Dušan ; Gál, P. ; Kotouč, M. ; Dymáček, Petr ; Masák, Jan ; Kopačka, Ján
Thermal and creep analysis of the VVER-1000 reactor pressure vessel (RPV) was performed at high temperatures caused by fuel melting during severe accident. First, the integral code ASTEC was applied simulating severe accident evolution since an initiating event up to a hypothetical radioactive release into the environment. The ASTEC outputs including the remaining RPV wall thickness, the heat flux achieved and the temperature profile in the ablated vessel wall served as boundary conditions for the consequent assessment of RPV integrity carried out with the aid of finite element method (FEM). The FEM analysis was performed including the creep behaviour of RPV material using a complex creep probabilistic exponential model with damage. The objective of the analysis was to computationally assess emergency condition and, on this basis, to propose a general methodology for evaluating the integrity of RPV at high temperatures due to fuel melting during severe accident.
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Severe accidents of third generation pressurized water reactors
Nečas, Karel ; Foral, Štěpán (referee) ; Černý, Tomáš (advisor)
The bachelor thesis focuses on the development of global nuclear energy. It clearly describes the development and division of nuclear facilities used for electricity production. The theoretical part of the thesis describes the division of nuclear facilities according to the development generations, the types are discussed in terms of technology and principle of operation. The operating conditions of nuclear reactors are described in detail, with emphasis on emergency conditions. The next part of the thesis focuses on the LOCA accident type for third generation pressurized water reactors. This thesis also includes an analysis of different approaches od the computation codes used for modelling various conditions of the nuclear power plants. The practical part of the bachelor thesis describes nuclear reactor APR1400. It provides its elementary parameters. The calculation code MELCOR was used for modelling this type of the nuclear reactor. The sensitivity analysis of the severe accident was performed using selected parameters. This analysis describes the influence of these parameters on the hydrogen production, the process of damaging of the active zone, and the reactor vessel melting time.
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Provisions for mitigation of consequences in case of major accidents in GFR nuclear reactors
Mlčúch, Adam ; Suk, Ladislav (referee) ; Martinec, Jiří (advisor)
This thesis deals with the severe accident of the gas-cooled fast reactor GFR. At the beginning of the study there is a review of the gas-cooled fast reactor subject. Next part is focused on description of possible solutions for severe accidents with emphasis on the solution applied in the Generation III+ reactors. Chapters that deal with material and thermal balance with severe accident of GFR demonstration unit, along with the chapter which analyses features of the corium, create a basis for the conceptual design of core catcher of GFR demonstration unit, which forms the final part of this thesis.
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