Intergranular stress-assisted corrosion cracking of austenitic alloys in water-cooled nuclear reactors

Intergranular stress-assisted corrosion cracking of austenitic alloys in water-cooled nuclear reactors [electronic resource]

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Bibliographic Details
Online Access: Online Access
Corporate Author: Argonne National Laboratory (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Argonne, Ill. : Oak Ridge, Tenn. : Argonne National Laboratory ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1974.
Subjects:
*bwr Type Reactors > Pipelines.
Primary Coolant Circuits.
Pipes.
*stainless Steel-347 > Stress Corrosion.
*pipelines > Cracks.
*pwr Type Reactors > Pipelines.
*pipe Joints > Cracks.
*inconel 600 > Stress Corrosion.
*stainless Steel-304 > Stress Corrosion.
*stainless Steel-304l > Stress Corrosion.
*incoloy 800 > Stress Corrosion.

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Call Number: E 1.99:conf-7309129--1
E 1.99:conf-7309129--1 Available

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