Published April 1980
| Version v1
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Thermal evaluation facility for LMFBR spent fuel transport
Description
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
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A06/MF A01.Files
11555466.pdf
Files
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Additional details
Publishing Information
- Imprint Pagination
- 107 p.
- Report number
- SAND--79-1366
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11555466
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CASKS; FUEL ASSEMBLIES; HEAT TRANSFER; LMFBR TYPE REACTORS; MOCKUP; PERFORMANCE TESTING; SPENT FUEL ELEMENTS; THERMAL STRESSES
- Descriptors DEC
- BREEDER REACTORS; CONTAINERS; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUEL ELEMENTS; LIQUID METAL COOLED REACTORS; REACTOR COMPONENTS; REACTORS; STRESSES; STRUCTURAL MODELS; TESTING