Review of environmental effects on fatigue crack growth of austenitic stainless steels

Review of environmental effects on fatigue crack growth of austenitic stainless steels [electronic resource]

Show other versions (1)

Fatigue and environmentally assisted cracking of piping, pressure vessel cladding, and core components in light water reactors are potential concerns to the nuclear industry and regulatory agencies. The degradation processes include intergranular stress corrosion cracking of austenitic stainless ste...

Full description

Saved in:
Bibliographic Details
Online Access: Online Access
Corporate Author: U.S. Nuclear Regulatory Commission (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Rockville, Md. : Oak Ridge, Tenn. : U.S. Nuclear Regulatory Commission ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, 1994.
Subjects:
Pipes.
Corrosion Fatigue.
Crack Propagation.
Bwr Type Reactors.
Pwr Type Reactors.
Austenitic Steels.
Pressure Vessels.
Reactor Cores.
Intergranular Corrosion.
Stress Corrosion.
Data Analysis.
Water Chemistry.
Primary Coolant Circuits.
Data.
Specific Nuclear Reactors And Associated Plants.
Materials Science.

Internet

Online Access

Online

Holdings details from Online
Call Number: E 1.99: anl--94/1
E 1.99: anl--94/1 Available

Similar Items