Recovery of Strategic High-Value Fission Products from Spent Nuclear Fuel During Reprocessing
- 1. Department of Chemical Engineering, University of Manchester, Oxford Road, Manchester, Greater Manchester, M13 9 PL, GB
- 2. University of Central Lancashire, Fylde Road, Preston, Lancashire, PR1 2HE, GB
Description
Nuclear fission has been identified as a key technology for the Net Zero transition, but high costs and concerns of radioactive wastes hinder wider uptake, and fuel cycle inefficiencies hamper the technology's long-term sustainability. Closing the fuel cycle through spent nuclear fuel (SNF) reprocessing is the primary method of improving sustainability, but high costs and proliferation concerns limit uptake. Current reprocessing technologies recover only the bulk U and Pu in SNF for further energy generation as MOX (mixed oxide) fuel, leaving behind a wide range of untapped, naturally scarce, high-demand, and -value fission product resources. By recovering these resources, such as the platinum group metals (PGMs – Ru, Rh, Pd, Ag), rare earth elements (REEs – Y, La to Dy), and noble gases (He, Kr, Xe), and various other useful isotopes, from SNF during reprocessing operations, the high costs incurred have the potential to be partially or completely offset, in addition to benefits from reducing waste volumes. This paper provides an overview of this concept with exploration of the most promising candidate targets and feeds within reprocessing, and the necessary actions that will be required to see this concept come to fruition in the coming decades.
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Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 7 p.
- Journal Title
- EPJ. Web of Conferences
- Journal Volume
- 317
- Journal Page Range
- 01004.1-01004.7
- ISSN
- 2100-014X
Conference
- Title 6. International ATALANTE Conference on Nuclear Chemistry for Sustainable Fuel Cycles (ATALANTE-2024)
- Acronym
- ATALANTE-2024
- Dates
- 1-6 Sep 2024
- Place
- Avignon (France)
- Website https://www.epj-conferences.org/articles/epjconf/abs/2025/02/contents/contents.html
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S98: NUCLEAR DISARMAMENT, SAFEGUARDS AND PHYSICAL PROTECTION;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COST; COST ESTIMATION; EXPLORATION; FISSION PRODUCTS; FUEL CYCLE; FUEL REPROCESSING PLANTS; KRYPTON; MATERIALS RECOVERY; MIXED OXIDE FUELS; PLATINUM; PROLIFERATION; RADIOACTIVE WASTES; RARE EARTHS; REPROCESSING; SPENT FUELS; URANIUM RECYCLE
- Descriptors DEC
- CLOSED FUEL CYCLE; ELEMENTS; ENERGY SOURCES; FLUIDS; FUEL CYCLE; FUELS; GASES; ISOTOPES; MANAGEMENT; MATERIALS; METALS; NONMETALS; NUCLEAR FACILITIES; NUCLEAR FUELS; PLATINUM METALS; PROCESSING; RADIOACTIVE MATERIALS; RARE GASES; REACTOR MATERIALS; SEPARATION PROCESSES; SOLID FUELS; TRANSITION ELEMENTS; WASTE MANAGEMENT; WASTE PROCESSING; WASTES
Optional Information
References
- 34 refs.