POSTIRRADIATION EXAMINATION OF EBR-I CORE IV PROTOTYPE FUEL RODS. Final Report
BS>Four EBR-I Mark-IV prototype fuel rods containing slugs of plutonium- 1 wt% aluminum alloy were irradiated in the EBR-I reactor at central fuel temperatures from 342 to 386 deg C and at burnups up to 0.1 at.%. No appreciable slumping of the fuel occurred during irradiation, and no significant density nor dimensional changes were observed. Variation of the initial fuel-cladding annulus from 0.004 to 0.019 in. had no significant effect on the slumping behavior, but the larger clearance did allow the fuel pin to bow to a greater extent than that observed in fuel rods with smaller annuli. A niobium restrainer effectively decreased the amount of bowing from that found in a rod with a similar annulus, but did not appear to offer any greater restriction than that provided by a small 0.004-in. annulus. (auth)
- Research Organization:
- Argonne National Lab., Ill.
- DOE Contract Number:
- W-31109-ENG-38
- NSA Number:
- NSA-18-004297
- OSTI ID:
- 4124896
- Report Number(s):
- ANL-6670
- Country of Publication:
- United States
- Language:
- English
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