Fuel Cycle Archives

Recycling Nuclear Waste into a Strategic Asset

Zeno will partner with Argonne National Laboratory (ANL) to demonstrate the capabilities of a pyro-aqueous hybrid strontium separation process to provide technical data for Zeno to explore scale up in support of Zeno’s RPS designs. ANL’s Chemical and Fuel Cycle Technologies (CFCT) division have extensive experience in developing separation technologies for UNF recycling, in addition to medical isotope separation and purification. This project will generate successful flowsheet development to reduce the volume, heat load, and cost for UNF.

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Analysis of NuCycle® Flowsheet for Waste Stream Characterization, Curio Solutions

Curio will partner with Pacific Northwest National Laboratory (PNNL) to conduct an analysis of the NuCycle® flowsheet that will allow the generation of quantities and classification of anticipated waste streams and recommendations on waste forms most suitable to sequestering the generated waste streams. Results of the project would be used to determine the approach to managing waste from a pilot demonstration of NuCycle® to be performed in 2027.

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Metatomic Molten Salt Immersed Hydrochlorination Subsystem Characterization, Metomic

Savannah River National Laboratory (SRNL) will provide the requisite expertise and spent fuel handling capability to enable the laboratory scale assessment and demonstration. The data generated at laboratory scale would provide confirmation of feasibility and basis for scaling to an industrial scale capability.

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Redox Potentials for Proliferation-Hardened Actinide Recovery in NuCycle, Curio Solutions

The project will acquire reduction potentials for NuCycle’s electrolysis process that will allow: (1) the implementation of safeguards by design, and (2) the generation of a coextracted actinide product meeting recycle specifications.

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Plasma Separation Process Feasibility Study for the Commercial Enrichment of Gadolinium-157, Exelon Generation

The objective of this project was to determine if currently available technology can be used to modernize the PSP to a level of cost-effectiveness to realize the potential cost saving in the nuclear fuel cycle.

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