Edge blockage in a 19-pin sodium-cooled bundle. [LMFBR]
Conference
·
OSTI ID:5356275
To assess the effect of partial flow blockages on the local temperature distributions in LMFBR fuel assemblies, several experiments have been carried out at the Thermal-Hydraulic Out-of-Reactor Safety (THORS) Facility at the Oak Ridge National Laboratory. Two kinds of flow blockages have been investigated: (1) six-channel internal blockage for which the blocked channels are not adjacent to the duct wall, and (2) 14-channel edge blockage for which some of the blocked channels are adjacent to the wall. The larger edge blockage is generally more severe than the internal blockage due to higher temperature rises in the wake behind the blockage. The experimental results on the edge blockage are analyzed and presented.
- Research Organization:
- Oak Ridge National Lab., Tenn. (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 5356275
- Report Number(s):
- CONF-771120-8
- Country of Publication:
- United States
- Language:
- English
Similar Records
Sodium boiling tests in a 19-pin internally guard heated simulated LMFBR fuel assembly with a six-channel internal blockage: record of experimental data for THORS bundle 3C
Maximum wake temperature and Nusselt number behind blockages in sodium-cooled bundles
Out-of-pike experiments for fission gas release in LMFBR fuel subassemblies - gas release into blockage wake region with a wire-wrapped 37-pin bundle
Technical Report
·
Tue May 01 00:00:00 EDT 1979
·
OSTI ID:6053419
Maximum wake temperature and Nusselt number behind blockages in sodium-cooled bundles
Conference
·
Fri Dec 31 23:00:00 EST 1976
·
OSTI ID:5289681
Out-of-pike experiments for fission gas release in LMFBR fuel subassemblies - gas release into blockage wake region with a wire-wrapped 37-pin bundle
Journal Article
·
Sat Oct 31 23:00:00 EST 1981
· Am. Soc. Mech. Eng., (Pap.); (United States)
·
OSTI ID:5085362
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
BREEDER REACTORS
CONFIGURATION
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLOW BLOCKAGE
FUEL ASSEMBLIES
FUEL ELEMENTS
FUEL PINS
HEAT TRANSFER
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MOCKUP
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
SAFETY
STRUCTURAL MODELS
TEMPERATURE DISTRIBUTION
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BREEDER REACTORS
CONFIGURATION
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLOW BLOCKAGE
FUEL ASSEMBLIES
FUEL ELEMENTS
FUEL PINS
HEAT TRANSFER
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MOCKUP
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
SAFETY
STRUCTURAL MODELS
TEMPERATURE DISTRIBUTION