Experimental study on natural-convection boiling burnout in an annulus. [PWR; BWR]

Conference · Fri Jan 01 00:00:00 EST 1982

OSTI ID:6342399

Mishima, K; Ishii, M

An experimental study was performed on burnout heat flux at low flow rates for low-pressure steam-water upward flow in an annulus. The data indicated that a premature burnout occurred due to flow-regime transition from churn-turbulent to annular flow. It is shown that the burnout observed in the experiment is essentially a flooding-limited burnout and the burnout heat flux can be well reproduced by a nondimensional correlation derived from the previously obtained criterion for flow-regime transition. It is also shown that the conventional correlations for burnout heat flux at low mass velocities agree well with the data on circulation and entrainment-limited burnout.

• Research Organization: Kyoto Univ., Kumatori, Osaka (Japan). Research Reactor Inst.; Argonne National Lab., IL (USA)
• DOE Contract Number: W-31-109-ENG-38
• OSTI ID: 6342399
• Report Number(s): CONF-820901-8; ON: DE83007705
• Resource Relation: Conference: 7. international heat transfer conference, Munich, F.R. Germany, 6 Sep 1982; Other Information: Portions are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BURNOUT
TEST FACILITIES
BWR TYPE REACTORS
FUEL CANS
LOSS OF COOLANT
LOSS OF FLOW
HEAT TRANSFER
HYDRAULICS
PWR TYPE REACTORS
BOILING
NATURAL CONVECTION
REACTOR SAFETY
ACCIDENTS
CONVECTION
ENERGY TRANSFER
FLUID MECHANICS
MECHANICS
PHASE TRANSFORMATIONS
REACTOR ACCIDENTS
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled