Products tagged with 'potassium hydroxide'

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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.

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Potassium Hydroxide For PWR Primary Coolant pH Control: EPRI Program

Product Number: ED22-17394-SG

Author: Keith Fruzzetti, Dennis Hussey, Peter Chou, David Perkins

Publication Date: 2022

$20.00

This paper outlines and summarizes the robust testing and assessment program developed and implemented by the Electric Power Research Institute (EPRI), following upon an initial feasibility evaluation completed in 2015. A multi-year, multi-discipline program has been developed, incorporating significant industry input, to address the identified technical gaps in materials, fuels, chemistry, and radiation safety that need evaluation to support a plant demonstration in a Western-design PWR.

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The Effect Of Potassium Hydroxide Primary Water Chemistry On The IASCC Behavior Of 304 Stainless Steel

Product Number: ED22-17415-SG

Author: Michael Ickes, Peter Chou, Kai Chen, Gary Was

Publication Date: 2022

$20.00

The objective of this work was to compare irradiation-assisted stress corrosion cracking (IASCC) growth behavior in simulated pressurized water reactor (PWR) water with pH maintained with LiOH versus KOH. The U.S. nuclear industry is considering changing PWR primary water chemistries to use KOH in place of LiOH, as a means to ensure a stable supply chain and secure cost savings. This experiment will specifically investigate the impact of these alkali ions on the crack growth rate (CGR) and to examine the crack morphologies generated by the CGR experiment.

Products tagged with 'potassium hydroxide'

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

Potassium Hydroxide For PWR Primary Coolant pH Control: EPRI Program

The Effect Of Potassium Hydroxide Primary Water Chemistry On The IASCC Behavior Of 304 Stainless Steel

Association for Materials Protection and Performance