Multiphase Flow Dynamics 4 Nuclear Thermal Hydraulics /

Detalles Bibliográficos
Autor principal: Kolev, Nikolay Ivanov. (Autor)
Autor Corporativo: SpringerLink (Online service)
Formato: eBook
Lenguaje:English
Publicado: Berlin, Heidelberg : Springer Berlin Heidelberg : Imprint: Springer, 2009.
Edición:1st ed. 2009.
Materias:
Acceso en línea:https://doi.org/10.1007/978-3-540-92918-5
Tabla de Contenidos:
  • Heat release in the reactor core
  • Temperature inside the fuel elements
  • The #x201C;simple#x201D; steady boiling flow in a pipe
  • The #x201C;simple#x201D; steady three-fluid boiling flow in a pipe
  • Core thermal hydraulic
  • Flow boiling and condensation stability analysis
  • Critical multiphase flow
  • Steam generators
  • Moisture separation
  • Pipe networks
  • Some auxiliary systems
  • Emergency condensers
  • Core degradation
  • Melt-coolant interaction
  • Coolability of layers of molten reactor material
  • External cooling of reactor vessels during severe accident
  • Thermo-physical properties for severe accident analysis.