ISSN Online: 2377-424X
ISBN Print: 0-89116-299-2
International Heat Transfer Conference 7
NUCLEAR SAFETY HEAT TRANSFER
要約
The coolability of the cores of nuclear reactors
must be insured in any circumstances without significant
pollution of the environment. The development
of advanced safety computer codes describing the
accidental behavior of the primary circuit nedds a
better physical modeling of the coolant flows and
heat transfers.
The part I is devoted to the Pressurized Water Reactors: a brief review is presented on transient burnout, post burnout heat transfer and boil-off phenomena.
In part II, the safety heat transfer problems of fast breeder reactors are presented. Boiling, clad melting, fuel-sodium interactions and post accident heat removal problem are described.
The part I is devoted to the Pressurized Water Reactors: a brief review is presented on transient burnout, post burnout heat transfer and boil-off phenomena.
In part II, the safety heat transfer problems of fast breeder reactors are presented. Boiling, clad melting, fuel-sodium interactions and post accident heat removal problem are described.