Nondestructive examination of 51 fuel and reflector elements from Fort St. Vrain Core Segment 1
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. 400/sup 0/ to 750/sup 0/C. Fast neutron fluences varied from approx. 0.3 x 10/sup 25/ n/m/sup 2/ to 1.0 x 10/sup 25/ n/m/sup 2/ (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.
- Research Organization:
- General Atomic Co., San Diego, CA (USA)
- DOE Contract Number:
- AT03-76ET35300
- OSTI ID:
- 6404795
- Report Number(s):
- GA-A-16000; ON: DE81026555
- Country of Publication:
- United States
- Language:
- English
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CARBON
COMPUTER CALCULATIONS
ELEMENTS
ENRICHED URANIUM REACTORS
EQUIPMENT
FUEL ASSEMBLIES
GAS COOLED REACTORS
GRAPHITE
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
HTGR TYPE REACTORS
INSPECTION
MATERIALS
MATERIALS HANDLING EQUIPMENT
MATERIALS TESTING
NONDESTRUCTIVE TESTING
NONMETALS
PHYSICAL RADIATION EFFECTS
POWER REACTORS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR MATERIALS
REACTORS
REMOTE HANDLING EQUIPMENT
SHRINKAGE
STRESSES
TESTING
VRAIN REACTOR