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Potassium Hydroxide For PWR Primary Coolant pH Control: EPRI Program

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. 

Product Number: ED22-17394-SG
Author: Keith Fruzzetti, Dennis Hussey, Peter Chou, David Perkins
Publication Date: 2022
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“Western-design” pressurized water reactors (PWRs), for example those based on Westinghouse, Babcock & Wilcox, or Combustion Engineering designs and their licensed derivatives, use isotopically specific Li-7 (i.e., ≥ 99.94% 7Li as 7LiOH) for primary side at-temperature pH (pHT) control. Naturally occurring lithium cannot be used because the 6Li content would generate an untenable increase in tritium production (a significant radioactive effluent and waste concern). Naturally occurring potassium hydroxide (KOH) is a very promising alternative to 7LiOH. Potassium hydroxide is much more readily available (alleviating a significant concern associated with future supply vulnerability of 7LiOH) at a significantly lower cost (since no isotopic enrichment is required) and offers potential fuel performance and material degradation improvements. However, KOH has not been qualified for use in the Western-design PWR fleet; although, it has been successfully applied for several decades in the VVER fleet.




“Western-design” pressurized water reactors (PWRs), for example those based on Westinghouse, Babcock & Wilcox, or Combustion Engineering designs and their licensed derivatives, use isotopically specific Li-7 (i.e., ≥ 99.94% 7Li as 7LiOH) for primary side at-temperature pH (pHT) control. Naturally occurring lithium cannot be used because the 6Li content would generate an untenable increase in tritium production (a significant radioactive effluent and waste concern). Naturally occurring potassium hydroxide (KOH) is a very promising alternative to 7LiOH. Potassium hydroxide is much more readily available (alleviating a significant concern associated with future supply vulnerability of 7LiOH) at a significantly lower cost (since no isotopic enrichment is required) and offers potential fuel performance and material degradation improvements. However, KOH has not been qualified for use in the Western-design PWR fleet; although, it has been successfully applied for several decades in the VVER fleet.