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 the first core waits on

The reactor does not wait on this pyro plant. A first core of metallic U-Pu-Zr can be made from separated civilian plutonium and depleted uranium in a glovebox or hot-cell casting line, and the reactor can be licensed against that fuel. Oxide MOX plants (the industrial route that already puts plutonium into light-water reactors) press and sinter oxide pellets. They do not cast metal slugs. A metal line is its own facility.

What that first core does not solve is security. Separated plutonium in fresh fuel is Category I material until the fuel is irradiated enough to protect itself by dose rate. Co-recovery inside a future pyro plant does not make today’s clean cast fuel self-protecting. Guard force and accountancy are a site fact. They are described under Risks and Fuel Science.

Pyroprocessing is the plant that, later, takes discharged metal (and, after oxide reduction, LWR fuel) and returns a grouped uranium–transuranic alloy. That is new fuel, not a pure plutonium product. It is also where minor actinides become difficult: americium is volatile during injection casting of metal fuel, so a casting step that works for U-Pu-Zr can lose americium unless the process is built for that loss. Minor-actinide recycle is a chemistry problem on top of the electrorefiner, not an automatic result of “burning waste.”

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):

• the chemistry is dry / molten salt, without large water inventories that dominate criticality and hydrogen-risk discussions;
• plutonium can only be co-recovered with other actinides (see liquid cadmium cathode) — favourable for process-level proliferation resistance relative to pure Pu product streams, not a substitute for safeguards;
• the flowsheet matches injection-cast metal fuel routes demonstrated with metallic fuel programmes.

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.

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:

• a metal U-Pu-Zr fabrication line for the first cores (separate from oxide MOX plants, and on the critical path even if pyro is deferred)
• americium retention during injection casting, if minor actinides are to stay in the fuel
• remote fabrication quality and cost at scale
• pyroprocessing throughput and availability
• safeguards and real-time material accountancy
• physical protection of fresh plutonium-bearing fuel, which does not scale down with plant output
• waste-form qualification and disposal pathways
• facility licensing and public/regulatory acceptance
• economics relative to once-through storage or aqueous recycle

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.