Effects of duct configuration on flow and temperature structure in sodium-cooled 19-rod simulated LMFBR fuel bundles with helical wire-wrap spacers

Conference · Thu Jan 01 00:00:00 EST 1976

OSTI ID:7269719

Wantland, J L; Fontana, M H; Gnadt, P A; Hanus, N; MacPherson, R E; Smith, C M

Thermal-hydrodynamic testing of sodium-cooled 19-rod simulated LMFBR fuel bundles is being conducted at the O ak Ridge National Laboratory in the Fuel Failure Mockup (FFM), an engineering-scale high-temperature sodium facility which provides prototypic flows, temperatures and power densities. Electrically heated bundles have been tested with two scalloped and two hexagonal duct configurations. Peripheral helical flows, attributed to the spacers, have been observed with strengths dependent upon the evenness and relative sizes of the peripheral flow areas. Diametral sodium temperature profiles are more uniform with smaller peripheral flow areas.

• Research Organization: Oak Ridge National Lab., Tenn. (USA)
• OSTI ID: 7269719
• Report Number(s): CONF-760816-5; TRN: 76-018719
• Resource Relation: Conference: National heat transfer conference, St. Louis, MO, USA, 8 Aug 1976
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
FUEL ELEMENT CLUSTERS
FLUID FLOW
TEMPERATURE DISTRIBUTION
LMFBR TYPE REACTORS
CONFIGURATION
DUCTS
HYDRAULICS
MOCKUP
SPACERS
BREEDER REACTORS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
FUEL ASSEMBLIES
LIQUID METAL COOLED REACTORS
MECHANICS
REACTORS
STRUCTURAL MODELS
220500* - Nuclear Reactor Technology- Environmental Aspects