Fuel-rod/support-grid scratching and friction (LWBR development program)
Technical Report
·
OSTI ID:5801078
Equations have been developed from test measurements for use in defining the anticipated range of potential fuel-rod scratch depths resulting from rod-grid interaction during LWBR module assembly. Correlations estimating the friction coefficients expected between the AM-350 support grids and the Zircaloy-clad fuel rods have also been derived. Experience with the use of a colloidal graphite suspension as a clad lubricant to facilitate fuel-rod installation and minimize clad assembly damage is described. Inspection results concerning clad scratches which occurred during the actual rod-installation phase of LWBR assembly appear consistent with the subject test findings.
- Research Organization:
- Bettis Atomic Power Lab., West Mifflin, PA (USA)
- DOE Contract Number:
- EY-76-C-11-0014
- OSTI ID:
- 5801078
- Report Number(s):
- WAPD-TM-1164
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
DAMAGE
ENRICHED URANIUM REACTORS
FRICTION
FUEL ASSEMBLIES
FUEL ELEMENTS
FUEL RODS
MECHANICAL STRUCTURES
POWER REACTORS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
SHIPPINGPORT REACTOR
SLIDING FRICTION
SUPPORTS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WEAR
210500* -- Power Reactors
Breeding
DAMAGE
ENRICHED URANIUM REACTORS
FRICTION
FUEL ASSEMBLIES
FUEL ELEMENTS
FUEL RODS
MECHANICAL STRUCTURES
POWER REACTORS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
SHIPPINGPORT REACTOR
SLIDING FRICTION
SUPPORTS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WEAR