Nondestructive examination of 51 fuel and reflector elements from Fort St. Vrain Core Segment 1
Description
Fifty-one fuel and reflector elements irradiated in core segment 1 of the Fort St. Vrain High-Temperature Gas-Cooled Reactor (HTGR) were inspected dimensionally and visually in the Hot Service Facility at Fort St. Vrain in July 1979. Time- and volume-averaged graphite temperatures for the examined fuel elements ranged from approx. 4000 to 7500C. Fast neutron fluences varied from approx. 0.3 x 1025 n/m2 to 1.0 x 1025 n/m2 (E > 29 fJ)/sub HTGR/. Nearly all of the examined elements shrank in both axial and radial dimensions. The measured data were compared with strain and bow predictions obtained from SURVEY/STRESS, a computer code that employs viscoelastic beam theory to calculate stresses and deformations in HTGR fuel elements
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A06/MF A01.
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Additional details
Publishing Information
- Imprint Pagination
- 102 p.
- Report number
- GA-A--16000
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 12632911
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTER CALCULATIONS; FUEL ASSEMBLIES; GRAPHITE; INSPECTION; NONDESTRUCTIVE TESTING; PHYSICAL RADIATION EFFECTS; REACTOR CORES; REACTOR MATERIALS; REMOTE HANDLING EQUIPMENT; SHRINKAGE; STRESSES; VRAIN REACTOR
- Descriptors DEC
- CARBON; ELEMENTS; ENRICHED URANIUM REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HTGR TYPE REACTORS; MATERIALS TESTING; NONMETALS; POWER REACTORS; RADIATION EFFECTS; REACTOR COMPONENTS; REACTORS; TESTING