Two-dimensional computational modeling of sodium boiling in simulated LMFBR fuel-pin bundles

Conference · Thu Jan 01 04:00:00 EST 1981

OSTI ID:6463741

Dearing, J F

Extensive sodium boiling tests have been carried out in two simulated LMFBR fuel pin bundles in the Thermal-Hydraulic Out-of-Reactor Safety (THORS) Facility at Oak Ridge National Laboratory. Experimental results from a 19-pin bundle (THORS Bundle 6A) have been previously reported, and experimental results from a 61-pin bundle (THORS Bundle 9) will be reported soon. The results discussed here are from the 19-pin bundle. Preliminary analysis has shown that the computational methods used and conclusions reached are equally valid for the 61-pin bundle, as well as the 19-pin in-reactor Sodium Loop Safety Facility (SLSF) W-1 experiment. The main result of THORS sodium boiling experimentation is that boiling behavior is determined by two-dimensional effects, i.e., the rates of mass, momentum and energy transfer in the direction perpendicular to the axes of the fuel pins.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 6463741
• Report Number(s): CONF-810606-54; ON: DE81023267
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ALKALI METALS
BOILING
BREEDER REACTORS
ELEMENTS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
FUEL ASSEMBLIES
HEAT TRANSFER
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MECHANICS
METALS
MOCKUP
PHASE TRANSFORMATIONS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
SODIUM
STRUCTURAL MODELS
TEST FACILITIES