Senior engineer, Hanford Engineering Development Laboratory, Richland, WA
Pages: 10 Published: Jan 1985
The data base of Type 316 stainless steel 20% cold-worked cladding swelling measurements from mixed-oxide fuel pins irradiated in Experimental Breeder Reactor-II (EBR-II) has been extended to a fast (E > 0.1 MeV) fluence of 17 × 1022 neutrons (n)/cm2. Previously, the data base from actual fuel pins included only developmental and Fast Flux Test Facility (FFTF) first core cladding of 5.84 mm (0.230 in.) diameter irradiated to a maximum fast fluence of 13 × 1022 n/cm2. Recent data includes FFTF fourth core material and cladding samples 7.37 mm (0.290 in.) in diameter that were taken from various advanced oxide experiments. Differences in incubation parameter between the swelling of first and fourth core material were at first attributed to heat-to-heat differences, but later were shown to be more properly attributed to different experimental and cladding fabrication parameters. Peak swelling values have now reached 40% volume change.
Swelling in cold-worked Type 316 stainless steel ducts used in EBR-II has also been evaluated using coupons cut or punched from irradiated duct faces. Substantial differences in swelling between faces, which reflect the local reactor environment, have been observed. More recently, duct material at the same maximum fluence as that of the fuel pin cladding has been added to the data base and compared to the swelling of EBR-II cladding.
radiation, swelling, cladding, ducts, fast breeder reactor, stainless, steels, fuel pins
Paper ID: STP37362S