Symposium on Structural Materials for Service at Elevated Temperatures in Nuclear Power Generation, November 30-December 3, 1975, Houston, Texas: held as part of the ASME winter annual meeting
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CreepRupture Correlations for Type 304 Stainless Steel Heat 9T2796
Correlation of the Microstructure with the Creep and Tensile Properties of AISI
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20 percent cold-worked 316 stainless steel aging Alloy American Society analysis annealed annealed material ASME ASTM austenitic austenitic stainless steels bainite behavior carbide carbon CM CM CM component constant constitutive equations correlation corrosion Cr-1 Mo Steel crack growth rate creep rate creep strain creep tests creep-rupture cycle decarburization decrease deformation deg F ductility EBR-II effect of hold-time Elevated Temperature elongation embrittlement extensometer ferrite grain boundary heat treatment High Temperature hold period Inconel increase isothermal isothermally annealed LMFBR mechanical properties Metals microstructure minute hold-time normalized and tempered Nuclear parameter plastic strain power law predicted ratchetting Reactor sodium specimens steam strain rate stress corrosion cracking stress-rupture stress-strain curves subgrain substructure Table tensile properties tensile strength tensile tests tertiary creep test temperature thermal true stress tubing type 304 stainless unirradiated values weld yield strength