Lead‑cooled reactors as water alternatives: corrosion lessons for nuclear designers
Reviewed by Tom Sullivan

First reported on New Civil Engineer
30 Second Briefing
Researchers in Sweden have characterised how stainless steel corrodes in contact with liquid lead, providing data critical for structural components in lead‑cooled fast reactors proposed as alternatives to pressurised water designs. The work focuses on corrosion mechanisms at the steel–lead interface, including dissolution and oxide layer behaviour, which directly affect cladding integrity, vessel wall thickness allowances and inspection intervals. Findings are expected to inform material selection, allowable temperature windows and safety margins for future Generation IV lead‑cooled reactor projects.
Technical Brief
- Liquid lead coolant allows operation at near‑atmospheric pressure, reducing primary circuit pressure vessel demands.
- Findings can feed into thermo‑mechanical design of reactor vessels, heat exchangers and fuel assemblies using lead coolants.
- Scope appears limited to specific stainless steel compositions and laboratory conditions, not full‑scale reactor environments.
Prepared by collating external sources, AI-assisted tools, and Geomechanics.io’s proprietary mining database, then reviewed for technical accuracy & edited by our geotechnical team.
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