Lithium hydroxide from Li-7 as used in thermal reactors

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Lithium hydroxide (LiOH) made from Li-7 is utilized in light water reactors primarily as an anti-corrosion additive to enhance the longevity of reactor components. The U.S. lacks lithium separation facilities, leading to speculation that Li-7 is sourced from Russia and China. Li-7 is preferred over natural lithium, which contains both Li-6 and Li-7 isotopes, due to Li-6's potential to produce tritium in neutron-rich environments. The use of LiOH helps maintain a pH above 6.9 in the coolant to prevent nickel dissolution and crud deposition. Current U.S. efforts are underway to enrich lithium and produce separate streams of Li-6 and Li-7.
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So I read that lithium hydroxide made from Li-7 is used as an anti-corrosion additive in light water reactors purely for the "longevity" and "well being" of the vessel and structural auxiliary elements like steam pipes etc.

Lithium separation is a rather chemically "nasty" task if using the COLEX process , I see there are others as well but much less effective. Given US no longer operates Li separation facilities where do US reactors get their Li-7 needed inventory?
I would assume Russia and China.
And why only Li-7 is used but not ordinary Lithium containing both the Li-6 and Li-7 stable isotopes?
Is it because Li-6 in a neutron rich environment (the core) would produce too much Tritium?, Because chemically I would suspect that using ordinary Lithium instead of Li-7 for the lithium hydroxide solution would make no difference in the chemical anti corrosion properties?

Comments are welcome, thanks.
 
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LiOH is used as a buffer for soluble H3BO3 in PWR primary coolant. The goal is to achieve a pH > 6.9, and preferably ~7.1 to 7.4 (at ~300°C), in order to prevent dissolution of Ni from steam generator tubing (and stainless steel cladding on carbon steel PV and other components) as well as crud deposition in the core. Zn is also injected into the coolant to suppress Ni dissolution.

Li in LiOH is enriched in 7Li for the reason one cited above, that 6Li experiences (n,α) reaction resulting in T production.

Russia is a source and China is a potential source. There is currently a program in the US to enrich Li, or rather produce separate streams of 6Li and 7Li.

Russian VVER systems have used KOH for the same purpose.

One can reduce the demand of LiOH by reducing the required concentration of H3BO3 through enrichment of 10B in the boric acid. However, one must weight that against hypothetical boron dilution events and the reactivity insertion accidents.

Some background
http://www.world-nuclear.org/information-library/current-and-future-generation/lithium.aspx
 
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