[go: up one dir, main page]
More Web Proxy on the site http://driver.im/

Jacobs, 1990 - Google Patents

Grain-Boundary Segregation and IGSCC in Cold-Worked Type 304 SS

Jacobs, 1990

Document ID
2931179871695349766
Author
Jacobs A
Publication year
Publication venue
Corrosion

External Links

Snippet

Applied-potential constant extension rate tensile (CERT) tests were conducted on unirradiated, mill-annealed type 304 (UNS S30400) stainless steel, in an attempt to reproduce irradiation-assisted intergranular stress corrosion cracking (IGSCC) in the …
Continue reading at meridian.allenpress.com (other versions)

Classifications

    • CCHEMISTRY; METALLURGY
    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22FCHANGING THE PHYSICAL STRUCTURE OF NON-FERROUS METALS AND NON-FERROUS ALLOYS
    • C22F1/00Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working
    • C22F1/10Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working of nickel or cobalt or alloys based thereon
    • CCHEMISTRY; METALLURGY
    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22CALLOYS
    • C22C14/00Alloys based on titanium
    • CCHEMISTRY; METALLURGY
    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22CALLOYS
    • C22C19/00Alloys based on nickel or cobalt

Similar Documents

Publication Publication Date Title
Bruemmer et al. Microstructural and microchemical mechanisms controlling intergranular stress corrosion cracking in light-water-reactor systems
EP0515112B1 (en) Corrosion resistant high chromium stainless steel alloy and method of reducing stress corrosion cracking
Rebak et al. Resistance of Ferritic FeCrAl alloys to stress corrosion cracking for light water reactor fuel cladding applications
Jacobs Grain-Boundary Segregation and IGSCC in Cold-Worked Type 304 SS
Jacobs et al. Low-temperature annealing: a process to mitigate irradiation-assisted stress corrosion cracking
Chopra et al. Crack growth rates and fracture toughness of irradiated austenitic stainless steels in BWR environments.
Singh et al. Influence of Minor Additions of La, Ce, and Nd on the Mechanical and Corrosion Behavior of Aluminum Bronze in HNO3 Solution
Fujita et al. Stress corrosion cracking of sensitized type 304 stainless steel in high temperature water under gamma ray irradiation
Farmer et al. Survey of degradation modes of candidate materials for high-level radioactive-waste disposal containers
Ehrlich et al. Characterization and Assessment of Ferritic Martensitic Steels
McIlree et al. Effects of Variations of Carbon, Sulfur and Phosphorus on the Corrosion Behavior of Alloy 600
Thomas et al. The failure of stressed zircaloy in aqueous chloride solutions
Nikolaeva et al. Mechanism of the drop in the dependence of yield stress on neutron irradiation dose for low-alloy steel
Hawthorne Further Observations on A533-B Steel Plate Tailored for Improved Radiation Embrittlement Resistance
Spitznagel et al. Annealing of irradiation damage in high-copper ferritic steels
Takaku et al. Combined effects of neutron irradiation and hydrogen absorption on tensile properties and fracture mode of steels for nuclear pressure vessel
Odette et al. Anomalous hardening in model alloys and steels thermally aged at 290 C and 350 C: implications to low flux irradiation embrittlement
Nakanishi et al. Creep properties of Hastelloy-X in impure helium environments
Hwang Embrittlement mechanisms of nickel-base alloys in water
Yonezawa et al. Improvement of IASCC resistance for austenitic stainless steels in PWR environment
De et al. Electrochemical corrosion behavior of alloy 400: intergranular corrosion in acidic Na2SO4 solutions
Karantonidis Effect of Aging on Corrosion-induced Hydrogen Trapping of Aluminum Alloy 2024
US3427210A (en) Method of producing alloys of zirconium with iron,vanadium and chromium for use in nuclear reactors cooled with an organic coolant
Hesterberg Processes Responsible for the Mitigation of IASCC Susceptibility Following the Post-Irradiation Annealing of Austenitic Stainless Steels
Garr et al. Effects of microstructure on swelling and tensile properties of neutron-irradiated types 316 and 405 stainless steels