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ReCore-Processing

ReCore-Processing is the fuel-cycle side of the ReCore engineering concept: a pyroprocessing-oriented pathway to recover actinides from metallic fuel (and from oxide LWR fuel after reduction) and return them as U-TRU-Zr metal fuel. It is intended to support the closed cycle described in Why? — converting existing nuclear materials into fuel without depending on scarce specialised forms such as HALEU or TRISO.

For investors, regulators, and engineers, the industrial fuel cycle is often a larger uncertainty than the reactor island itself: remote fabrication, pyroprocessing throughput, economics, safeguards, material accounting, and facility licensing. Those open questions sit at the centre of this page.

What goes into the plant as feed is explained under LWR spent nuclear fuel; long-lived transuranics (TRU) are why multi-recycle is of interest.

Metallic SFR fuel and molten-salt electrorefining are a natural technical fit. Compared with large aqueous plants (e.g. PUREX-style):

Technology readiness

TRL figures are estimates. Process steps have been demonstrated at pilot and engineering scale; a commercial multi-reactor pyro hub is not yet a commodity industry.

TechnologyEst. TRLNotes / heritage
Metal-fuel electrorefining7–8Fuel Conditioning Facility (FCF), Idaho National Laboratory — multi-tonne class electrorefining of irradiated EBR-II metal fuel
Liquid cadmium cathode (LCC) co-recovery6–7Demonstrated electrorefiner option for TRU co-deposition (no pure Pu product stream by process design)
Electrolytic oxide reduction (LWR bridge)6–7Pilot / engineering programmes (e.g. PRIDE / KAERI and related oxide-to-metal work)
Metal fuel fabrication (injection cast)6–7Metallic fuel programmes (EBR-II / IFR heritage); glovebox / hot-cell casting routes
Hot-cell remote handling8–9Mature industrial and R&D practice worldwide for irradiated fuel
Salt clean-up / fission-product removal6–7Engineering development alongside electrorefiners; zeolite / extraction options in literature and pilots
Ceramic / metallic waste forms6–7Lab-to-engineering waste-form programmes (e.g. sodalite-type and metallic forms)
Actinide R&D hot cells (EU)7–8Atalante (Marcoule / CEA) and related European fuel-cycle R&D infrastructure
FR fuel / pyro R&D (Japan)6–7Tokai and JAEA-class work on fast-reactor fuel and pyrochemical options
Integrated commercial pyro hub3–5Not routine industry; needs scale-up, licensing, safeguards, and financing

How spent fuel is pyroprocessed

The process is electrochemical recycle in molten salt, not aqueous solvent extraction. Feed can be metallic SFR fuel or LWR oxide assemblies after they are understood as spent nuclear fuel and reduced to metal.

  1. Head-end — Fuel is chopped. Metallic spent fuel goes to electrorefining. LWR oxide fuel is first reduced to metal (e.g. electrolytic oxide reduction) so it can enter the same salt bath.
  2. Electrorefining — Chopped metal sits in a basket in a molten salt (typically a LiCl–KCl eutectic at roughly 500 °C). An electric current dissolves the fuel. Uranium deposits on a solid cathode; plutonium and minor actinides deposit together on a liquid metal cathode (e.g. cadmium — the LCC), so pure Pu is not isolated.
  3. Salt clean-up — Fission-product “ash” is removed from the salt so the bath can be reused; those streams go to stable waste forms.
  4. Fuel refabrication — Recovered actinides (including TRU are alloyed with zirconium, cast into metal fuel slugs, sodium-bonded into cladding, and sealed for return to the reactor.

All of this is intended to run in shielded hot cells under inert gas (e.g. argon). The intended products are fresh U-TRU-Zr metal fuel and compact fission-product-dominated waste forms — not a once-through spent-fuel assembly left as-is. Throughput, yields, and plant economics remain open industrial questions.

Radiotoxicity and timescales

Once-through LWR spent fuel remains radiotoxic on a multi-hundred-thousand-year scale largely because of actinides / TRU. Multi-recycle of transuranics is intended to substantially reduce the long-term radiotoxic inventory requiring geological isolation, leaving a residual stream dominated by fission products (literature often discusses order-of 500-year horizons in simplified comparisons). That is a fuel-cycle goal, not a plant guarantee.

Open industrial challenges

Beyond laboratory and pilot steps, commercialisation would still need to resolve, among other things:

These are where many advanced fuel-cycle proposals struggle — and why this page is as important as the reactor description.

Facility model

A regional hub serving several reactor sites is a practical deployment model: concentrate safeguards, hot cells, and expertise rather than co-locating full recycle on every reactor pad. Footprint is expected to be much smaller than classical aqueous mega-plants, but exact area depends on throughput and national rules.