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National Repository of Grey Literature 2 records found  Search took 0.00 seconds. 
Engineering design of the Freeze Valve
 Zeman, Radek ; Martinec, Jiří (referee) ; Šen, Hugo (advisor)
This bachelor´s thesis deals with practical design of freeze valve for nuclear facilities from both calculation and construction point of view. Firstly, a brief analysis of technologies of fast neutron reactors and reactors with fuel dissolved in melted fluorine salts has been done. The author points out the advantages of their use that may result in becoming an important part of nuclear power engineering. Working fluids are taken from these reactors – liquid sodium and mixture of molten salts NaBF4-NaF. The author deals with choice of suitable construction materials and ways of heat-transfer from working fluid. Secondly, several construction solutions have been assessed and project documentation has been created for some of them. These designs include alternative shapes of valves and canals, where heat exchanging medium flows – Field tube and valve with helix canal. These concepts allow fast intake (conducting away) of heat into the working fluid and after verification on an experimental stand these valves could work in conditions of nuclear facilities. Times of cooling and heating for chosen designs and working fluids are calculated by previously derived dimensionless equations describing transient heat-transfer field with phase change supposing low Biot numbers.
Detailed record
Engineering design of the Freeze Valve
 Zeman, Radek ; Martinec, Jiří (referee) ; Šen, Hugo (advisor)
This bachelor´s thesis deals with practical design of freeze valve for nuclear facilities from both calculation and construction point of view. Firstly, a brief analysis of technologies of fast neutron reactors and reactors with fuel dissolved in melted fluorine salts has been done. The author points out the advantages of their use that may result in becoming an important part of nuclear power engineering. Working fluids are taken from these reactors – liquid sodium and mixture of molten salts NaBF4-NaF. The author deals with choice of suitable construction materials and ways of heat-transfer from working fluid. Secondly, several construction solutions have been assessed and project documentation has been created for some of them. These designs include alternative shapes of valves and canals, where heat exchanging medium flows – Field tube and valve with helix canal. These concepts allow fast intake (conducting away) of heat into the working fluid and after verification on an experimental stand these valves could work in conditions of nuclear facilities. Times of cooling and heating for chosen designs and working fluids are calculated by previously derived dimensionless equations describing transient heat-transfer field with phase change supposing low Biot numbers.
Detailed record

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