Open AccessPOSTIRRADIATION EXAMINATION OF EBR-I CORE IV PROTOTYPE FUEL RODS. Final Report
Author(s) -
R. Carlander,
Jean Kittel,
R.J. Dunworth
Publication year - 1963
Language(s) - English
Resource type - Reports
DOI - 10.2172/4124896
Subject(s) - rod , slumping , materials science , annulus (botany) , cladding (metalworking) , irradiation , composite material , core (optical fiber) , radiochemistry , nuclear engineering , nuclear physics , chemistry , geology , physics , engineering , medicine , alternative medicine , pathology , geomorphology
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
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