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Effect of Cold Work on Tensile Behavior of Irradiated Type 316 Stainless Steel
RL. Klueh
PJ. Maziasz
出版
ASTM International
, 1987
URL
http://books.google.com.hk/books?id=3Rp-zgEACAAJ&hl=&source=gbs_api
註釋
The effect of various levels of cold work on the tensile behavior of Type 316 stainless steel was investigated. Tensile specimens were irradiated in the Oak Ridge Research Reactor (ORR) at 250, 290, 450, and 500°C to produce a displacement damage of ~5 displacements per atom (dpa) and 40 atomic ppm He. Irradiation at 250 and 290°C caused an increase in yield stress and ultimate tensile strength and a decrease in ductility relative to unaged and thermally aged controls. The changes were greatest for the 20%-cold-worked steel and lowest for the 50%-cold-worked steel. Irradiation at 450°C caused a slight decrease in strength for all cold-worked conditions relative to the aged material. A large decrease was observed at 500°C, with the largest decrease occurring for the 50%-cold-worked specimen. No bubble, void, or precipitate formation was observed for specimens examined by transmission electron microscopy (TEM). The irradiation hardening was correlated with Frank-loop and "black-dot" damage. A strength decrease at 500°C was correlated with dislocation network recovery. Comparison of tensile and TEM results from ORR-irradiated steel with those from steels irradiated in the High Flux Isotope Reactor and the Experimental Breeder Reactor indicated consistent strength and microstructure changes.