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Fracture behavior of austenitic stainless steels irradiated in PWR
Authors:K. Fukuya  H. Nishioka  M. Kamaya  T. Torimaru
Affiliation:a Institute of Nuclear Safety System Inc., 64 Sata, Mihama-cho, Mikata-gun, Fukui 919-1205, Japan
b Nippon Nuclear Fuel Development, 2163 Narita-cho, Oarai-machi, Ibaraki 311-1313, Japan
Abstract:Fracture behavior of cold-worked 316 stainless steels irradiated up to 73 dpa in a pressurized water reactor was investigated by impact testing at −196, 30 and 150 °C, and by conventional tensile and slow tensile testing at 30 and 320 °C. In impact tests, brittle IG mode was dominant at −196 °C at doses higher than 11 dpa accompanying significant decrease in absorbed energy. The mixed IG mode, which was characterized by isolated grain facets in ductile dimples, appeared at 30 and 150 °C whereas the fracture occurred macroscopically in a ductile manner. The sensitivity to IG or mixed IG mode was more pronounced for higher dose and lower test temperature. In uniaxial tensile tests, IG mode at a slow strain rate appeared only at 320 °C whereas mixed IG mode appeared at both 30 and 320 °C at a fast strain rate. A compilation of the results and literature data suggested that IG fracture exists in two different conditions, low-temperature high-strain-rate (LTHR) and high-temperature low-strain-rate (HTLR) conditions. These two conditions for IG fracture likely correspond to two different deformation modes, twining and channeling.
Keywords:28.41.Qb   61.80.Hg   61.80.Bg   62.20.mj   62.20.mt
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