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Crack Initiation Testing of Neutron-irradiated Type 347 Stainless Steel in Simulated PWR with LiOH or KOH

Product Number: ED22-17414-SG

Author: Michael Ickes, Lijin Dong, Abdullah Sinjlawi, Gary Was

Publication Date: 2022

$20.00

The immediate objective of this experiment is to investigate the IASCC initiation behavior of Type 347 stainless steel in lithium hydroxide and potassium hydroxide water chemistries across a range of irradiation damage and stress levels. A further objective is to provide data supporting improved predictive capabilities of IASCC failures by assessing the radiation dose dependence of IASCC initiation. In power plant components like the baffle-former bolts, the crack initiation step of IASCC is the rate limiting step, taking much longer than crack propagation as a fraction of time to failure. The results of this study will also be directly beneficial to the U.S. nuclear industry by providing an understanding of IASCC susceptibility in potassium hydroxide water chemistry, which may provide cost savings and more secure supply chains to nuclear power plants.

Products tagged with 'crack initiation testing'

Crack Initiation Testing of Neutron-irradiated Type 347 Stainless Steel in Simulated PWR with LiOH or KOH

Association for Materials Protection and Performance