Published March 30, 1971
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Fuel rod finite element stress analysis: segmented flight reactor fuel versus S8DR fuel
Description
A finite element stress analysis has been performed to define the stresses which exist near the delta/epsilon boundary in the fuel rod. Seven analyses were performed including an S8DR fuel rod at BOL and during one magawatt operation, and a core test segmented fuel rod with 3.0, 4.5, and 6.0 inch segments and worst-case boundary locations. Results indicate that maximum tensile stresses induced in the core test fuel segments are at least 20 percent lower than those induced in the S8DR rod during BOL (600 KWT) operation and at least 35 percent lower than the S8DR rod during magawatt operation. (5 references) (U.S.)
Availability note (English)
MF available from INIS under the Report Number.
Files
Additional details
Publishing Information
- Imprint Pagination
- 42 p.
- Report number
- TI--759-240-035
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 6215670
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- FUEL RODS; STRESS ANALYSIS; S8DR REACTOR; TENSILE PROPERTIES; THERMAL STRESSES
- Descriptors DEC
- ENRICHED URANIUM REACTORS; FUEL ELEMENTS; MECHANICAL PROPERTIES; MOBILE REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SNAP REACTORS; SNAP 8 REACTOR; SPACE POWER REACTORS; STRESSES