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General corrosion and stress corrosion cracking of Alloy 600 in light water reactor primary coolants

Journal

JOURNAL OF NUCLEAR MATERIALS
Volume 524, Issue -, Pages 340-375

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ELSEVIER
DOI: 10.1016/j.jnucmat.2019.04.023

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The general corrosion and stress corrosion cracking behaviors of the nickel-base Alloy 600 in the primary high temperature aqueous coolants of light water cooled and moderated nuclear power reactors are reviewed. The compatible welding Alloys 182 and 82 as well as the high strength, precipitation hardened analogue, Alloy X-750, are also included. The emphasis is on what is known of the underlying science of these degradation phenomena rather than on the associated engineering consequences and remedies. (C) 2019 Published by Elsevier B.V.

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