Stress Corrosion Cracking and Crack Tip Characterization of Alloy X-750 in Light Water Reactor Environments

Stress corrosion cracking (SCC) susceptibility of Inconel Alloy X-750 in the HTH condition has been evaluated in high purity water at 93 and 288°C under Boiling Water Reactor Normal Water Chemistry (NWC) and Hydrogen Water Chemistry (HWC) conditions. SCC crack growth rates of approximately 1.1x10-7...

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Bibliographic Details
Main Authors: Gibbs, Jonathan Paul, Ballinger, Ronald
Other Authors: Massachusetts Institute of Technology. Nuclear Systems Enhanced Performance Program
Format: Technical Report
Published: Massachusetts Institute of Technology. Center for Advanced Nuclear Energy Systems. Nuclear Systems Enhanced Performance Program 2012
Online Access:http://hdl.handle.net/1721.1/75019