Lithium hydroxide from Li-7 as used in thermal reactors

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SUMMARY

Lithium hydroxide (LiOH) derived from Li-7 is utilized as an anti-corrosion additive in light water reactors to enhance the longevity of structural components such as steam pipes. The COLEX process for lithium separation is chemically challenging, and the U.S. currently sources its Li-7 inventory from Russia and China due to the closure of domestic separation facilities. Li-6 is avoided in reactor environments because it produces Tritium through (n,α) reactions, which can complicate reactor operations. The optimal pH for the primary coolant is maintained between 7.1 and 7.4 to prevent nickel dissolution and crud deposition.

PREREQUISITES
  • Understanding of lithium isotopes, specifically Li-6 and Li-7
  • Knowledge of light water reactor (LWR) operations
  • Familiarity with corrosion mechanisms in nuclear reactors
  • Awareness of coolant chemistry, including the role of H3BO3 and pH control
NEXT STEPS
  • Research the COLEX process for lithium separation and its alternatives
  • Study the effects of lithium isotopes on neutron interactions in reactors
  • Investigate the role of boron enrichment in reducing LiOH demand
  • Explore the use of potassium hydroxide (KOH) in Russian VVER systems
USEFUL FOR

Nuclear engineers, reactor operators, and professionals involved in the maintenance and optimization of light water reactors will benefit from this discussion.

artis
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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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