A Preliminary Hybrid Model of Irradiation-Assisted Stress Corrosion Cracking of 300 Series Stainless Steels in PWR Primary Environments

Author:

Eason E. D.,Ilevbare G.,Pathania R.

Publisher

John Wiley & Sons, Inc.

Reference29 articles.

1. R. Pathania “Crack Growth Rates in Irradiated Stainless Steels in BWR Internals”, Proc. 14th Intl. Conf. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, Virginia Beach, VA, Aug. 23-27, 2009, American Nuclear Society Order No. 700347 (2010) (CD-ROM)

2. E. D. Eason R. Pathania “A Preliminary Hybrid Model of Nickel Alloy SCC Propagation in PWR Primary Water Environments”, 14th Env. Deg. see [1] 2010

3. C. Guerre “SCC Crack Growth Rate of Cold-Worked Austenitic Stainless Steels in PWR Primary Water Conditions”, 13th Env. Deg. see [2] 2007

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