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In-Reactor Creep of Zr-2.5Nb Pages: 20 Published: Jan 1984
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View License Agreement Source: STP824-EB Abstract The anisotropy of irradiation creep of Zr-2.5Nb alloy tubes at 570 K has been investigated using creep of helical springs and stress relaxation of twisted rods and bent beams. These tests measure creep rate directly since strains associated with irradiation growth are absent. Creep rates from these tests and from results on creep of pressurized tubes reported in the literature can be correlated through consideration of the crystallographic texture, slip systems, and dislocation density of the Zr-2.5Nb tubing. A creep model based on glide of Keywords: zirconium alloys, nuclear industry, creep, stress relaxation, in-reactor, texture, springs, Zr-2.5Nb Paper ID: STP34476S Committee/Subcommittee: B10.02 DOI: 10.1520/STP34476S ASTM International is a member of CrossRef. | ||