Thermal evaluation facility for LMFBR spent fuel transport

Technical Report · Tue Apr 01 04:00:00 EST 1980

DOI:https://doi.org/10.2172/5437586· OSTI ID:5437586

Wesley, D A

A full-scale mock-up of a 217 pin breeder reactor fuel assembly in a cylindrical pipe was initially designed and constructed by Oak Ridge National Laboratory (ORNL). It was transferred to Sandia where it was extensively redesigned and modified. The 217 pin hexagonal core assembly was installed in a smaller diameter stainless steel pipe which more closely represents the diameter of a shipping canister or shipping cask basket wall. Two-hundred four of the tubes are electrically heated over an active length of 4-feet and the remaining thirteen are instrumented with multiple junction thermocouples which can be traversed axially. Thermocouples and heat-flux gauges are located on the hex core and canister perimeters at several axial locations.

• Research Organization: Sandia Labs., Albuquerque, NM (USA)
• DOE Contract Number: AC04-76DP00789
• OSTI ID: 5437586
• Report Number(s): SAND-79-1366
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
BREEDER REACTORS
CASKS
CONTAINERS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ASSEMBLIES
FUEL ELEMENTS
HEAT TRANSFER
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MOCKUP
PERFORMANCE TESTING
REACTOR COMPONENTS
REACTORS
SPENT FUEL CASKS
SPENT FUEL ELEMENTS
STRESSES
STRUCTURAL MODELS
TESTING
THERMAL STRESSES