The results obtained from the experimental investigation of Cr-Ni-Mo-V and Mn-Ni-Mo-V steel service properties used in the USSR reactor building, as well as the static crack resistance KIC versus reference temperature dependence and Paris kinetic diagrams of fatigue crack growth rate in air and water of high parameters, are given.

Issue Section:
Research Papers
Topics:
Fatigue cracks, Fracture (Materials), Nuclear power stations, Pressurized water reactors, Steel, Structural steel, Temperature effects, Water
This content is only available via PDF.
Copyright © 1991
 by The American Society of Mechanical Engineers
You do not currently have access to this content.