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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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The 4th generation of nuclear reactors
Mlčúch, Adam ; Šnajdárek, Ladislav (referee) ; Nerud, Pavel (advisor)
This thesis reviews the particular generations of nuclear reactors. The biggest part of the thesis focuses on the projects of the fourth generation reactors. The individual projects come out from the analysis of the international forum GIF. The last part is devoted to the detailed description of VHTR system and demonstration plant concept with reactor Antares.
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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.
|
|
|
The 4th generation of nuclear reactors
Mlčúch, Adam ; Šnajdárek, Ladislav (referee) ; Nerud, Pavel (advisor)
This thesis reviews the particular generations of nuclear reactors. The biggest part of the thesis focuses on the projects of the fourth generation reactors. The individual projects come out from the analysis of the international forum GIF. The last part is devoted to the detailed description of VHTR system and demonstration plant concept with reactor Antares.
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