dc.contributor |
Panella, Bruno |
dc.contributor |
Bertani, Cristina |
dc.contributor.author |
Aramayo Hernández, Clara Inés |
dc.date |
2013-07 |
dc.identifier.uri |
http://hdl.handle.net/2099.1/20453 |
dc.language.iso |
eng |
dc.publisher |
Universitat Politècnica de Catalunya |
dc.rights |
info:eu-repo/semantics/openAccess |
dc.subject |
Àrees temàtiques de la UPC::Energies::Energia nuclear::Centrals nuclears |
dc.subject |
Nuclear power plants -- Safety measures |
dc.subject |
Boiling water reactors -- Safety measures |
dc.subject |
Pressurized water reactors -- Safety measures |
dc.subject |
Centrals nuclears -- Mesures de seguretat |
dc.subject |
Reactors nuclears d'aigua bullent -- Mesures de seguretat |
dc.subject |
Reactors nuclears d'aigua a pressió -- Mesures de seguretat |
dc.title |
Steam jet direct condensation in a water suppression pool |
dc.type |
info:eu-repo/semantics/masterThesis |
dc.description.abstract |
Direct contact condensation (DCC) of a steam jet discharged into a subcooled water pool is
an efficient way to condensate a large quantities of water at high pressure and temperature
without introducing any complex device. This phenomenon is used in many nuclear
engineering fields, such as pressure suppression pool in Boiling Water Reactors (BWRs),
condensing pool in Pressurized Water Reactors (PWRs) and suppression tank in
International Thermonuclear Experimental Reactor (ITER).
Safety in nuclear facilities, like Nuclear Power Plant (NPP), is very important because of the
past occurrence of nuclear accidents such as Fukushima or Chernobyl. The constructors of
nuclear facilities, the operating energy companies in NPP and national regulators are well
aware of the importance of the safety aspect. DCC is applied to improve the safety in a BWR
on off-normal conditions and accident transients, such as a Loss of Coolant Accident
(LOCA).
This study will focus not only on the suppression pool in a Boiling Water Reactor (BWR) but
also on the suppression tank in the Vacuum Vessel Pressure Suppression System (VVPSS)
in ITER. |