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The testing described in this paper is part of a wider initiative by the Electric Power Research Institute (EPRI) to perform a due-diligence assessment to support possible application to plants and demonstrate the use of potassium hydroxide (KOH) in western Pressurized Water Reactors (PWRs). Lithium hydroxide (LiOH) is used in the primary coolant loop of PWRs to modify the pH of the coolant water. LiOH is most commonly used as the alkalizing substance as 7Li is already present in the waterchemistry as a by-product of the neutron reaction with boron (10B). To reduce the risk of accelerated corrosion of the Zircaloy fuel cladding material, there is an upper limit of 3.5 ppm for 7Li, although standard starting chemistry is typically 2 ppm. The amount of lithium is subsequently reduced during operation as the required level of boron is reduced due to fuel burnup through the fuel lifecycle.
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