作者: M.L. Grossbeck , P.J. Maziasz
DOI: 10.1016/0022-3115(82)90702-4
关键词: Neutron temperature 、 Fluence 、 Tensile testing 、 Titanium 、 Alloy 、 Materials science 、 Ultimate tensile strength 、 Irradiation 、 Metallurgy 、 Ductility 、 Nuclear and High Energy Physics 、 General Materials Science 、 Nuclear Energy and Engineering
摘要: Abstract An alloy of type 316 stainless steel with the addition 0.23% Ti (316 + Ti) has been irradiated in 20% cold-worked condition HFIR (a mixed fast and thermal neutron spectrum reactor) tested near irradiation temperature range 300–600°C. Tensile tests were performed following to fluence levels 0.63−2.1 × 10 26 n/m 2 (E > 0.1 MeV) helium 200–1000 at. ppm. The exhibited higher strength lower ductility than similarly SS). However, tensile elongation tends saturate increasing at 575°C whereas SS continues fall for fluences investigated. Reduction area is similar two alloys, shows completely ductile rupture 450°C below. differences are attributed influence TiC precipitates trapping matrix.