Nuclear reactor safety heat transfer / Owen Jones
Tipo de material:
TextoIdioma: en Series Proceedings of the International Centre for Heat and Mass Transfer ; 12Detalles de publicación: Washington : Hemisphere Publishing Corporation, c 1981Descripción: xix, 959 p. : il.;, 23 cm
| Tipo de ítem | Biblioteca de origen | Signatura | Estado | Fecha de vencimiento | Código de barras | Reserva de ítems |
|---|---|---|---|---|---|---|
LIBRO
|
Biblioteca de la Facultad de Ingeniería UNMDP | 66.045 66.045 J 38 (Navegar estantería(Abre debajo)) | Disponible | 7624 |
Apéndices
Incluye índices
Referencias al final de los capítulos
Accident initiation and clad relocation
Blockages in LMFBR subassemblies
Blowdown phase
Core disruptive accidents
Emergency cooling water ingection
Experimental methods in two-Phase flows
Ex-Vessel post accident heat removal
fuel motion
In-Vessel post accident heat removal
LMFBR System safety analysis
Loss of coolant accident
LWR system safety analysis
Natural convection cooling
Nuclear system safety modeling
Power reactor concepts and systems overview
Reflood and rewet heat transfer
Safety Issues-Thermal hydraulic considerations
Single- and two-Phase flow
Single- and two-Phase heat transfer
Sodium boiling
The accident at Three Mile Island
Transient response of light water reactors
Transient response of liquid metal fast breeder reactors
Vapor explosions