Subchannel based radiation heat transfer model in COBRA-TF

Conference · Fri Jun 01 00:00:00 EDT 1984

OSTI ID:6894338

Kohrt, R J; McCann, R A; Kelly, J M

COBRA-TF is a two-fluid, three-dimensional, thermal-hydraulic computer code designed to model the hot channel of a light-water reactor during the reflood phase of a loss-of-coolant accident. The reflood phase is characterized by a superheated vapor coolant containing dispersed liquid droplets. Heat transfer to the vapor and droplets is poor, resulting in high temperatures at the surface of the fuel rods. Because of the high temperatures, heat transfer by radiation may account for a large portion of the heat removed from the fuel rods.

• Research Organization: Pacific Northwest Lab., Richland, WA (USA)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 6894338
• Report Number(s): PNL-SA-12008; CONF-840614-101; ON: DE84015577
• Resource Relation: Conference: Annual meeting of the American Nuclear Society, New Orleans, LA, USA, 3 Jun 1984; Other Information: Portions are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
LOSS OF COOLANT
RADIANT HEAT TRANSFER
PWR TYPE REACTORS
C CODES
COMPUTER CODES
FUEL CHANNELS
REACTOR CHANNELS
THERMAL RADIATION
ACCIDENTS
ELECTROMAGNETIC RADIATION
ENERGY TRANSFER
HEAT TRANSFER
RADIATIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety