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The Intermediate Heat Exchanger for ESFR reactor primary circuit
Švihel, Miroslav ; Baláš, Marek (referee) ; Šen, Hugo (advisor)
The thesis is mainly focused on the design of the intermediate heat exchanger primary circuit of the reactor ESFR. Heat exchanger is calculated heat, hydraulic and strength and is finally processed part drawings. There are designed the basic dimensions of the tube bundle and container heat exchanger. There are included an overview of concepts and so far used types IHX at the nuclear power plants with fast reactors. There are also mentioned basic parameters of the project ESFR and evaluated the safety and operational reliability of the heat exchanger.
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Intermediate heat exchanger natrium - natrium
Kupčík, Petr ; Martinec, Jiří (referee) ; Šen, Hugo (advisor)
This paper deals with intermediate heat exchangers in nuclear power plants. First section of this paper is devoted to analysis and divide of construction designs of intermediate heat exchangers in commercial and experimental power plants. There is a description of thermal, hydraulic and strength calculations during projection of IHX in the second chapter. There has been made a blueprint of loop type IHX in the final chapter of this paper.
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The Intermediate Heat Exchanger for ESFR reactor primary circuit
Švihel, Miroslav ; Baláš, Marek (referee) ; Šen, Hugo (advisor)
The thesis is mainly focused on the design of the intermediate heat exchanger primary circuit of the reactor ESFR. Heat exchanger is calculated heat, hydraulic and strength and is finally processed part drawings. There are designed the basic dimensions of the tube bundle and container heat exchanger. There are included an overview of concepts and so far used types IHX at the nuclear power plants with fast reactors. There are also mentioned basic parameters of the project ESFR and evaluated the safety and operational reliability of the heat exchanger.
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|
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Intermediate heat exchanger natrium - natrium
Kupčík, Petr ; Martinec, Jiří (referee) ; Šen, Hugo (advisor)
This paper deals with intermediate heat exchangers in nuclear power plants. First section of this paper is devoted to analysis and divide of construction designs of intermediate heat exchangers in commercial and experimental power plants. There is a description of thermal, hydraulic and strength calculations during projection of IHX in the second chapter. There has been made a blueprint of loop type IHX in the final chapter of this paper.
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