ML21145A256

Advanced Reactors GEIS Docs - INL - HALEU Hybrid Zirconium Extraction (Zircex) Process

ML21145A256
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Issue date:	05/25/2021
From:	NRC
To:	NRC/NMSS/DREFS
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From: Giacinto, Joseph Sent: Tuesday, May 25, 2021 2:05 PM To: AdvancedReactors-GEISDocsPEm Resource

Subject:

INL - HALEU Hybrid Zirconium Extraction (ZIRCEX) Process Attachments: HALEU_ZIRCEXProcessFactSheet.pdf

The ZIRCEX process pilot plant at INLs INTEC facility Hybrid Zirconium Extraction (ZIRCEX) Process Recovering and downblending HEU from federally owned fuels T

DOEs HALEU Program enables he hybrid ZIRCEX (short The Hybrid Process ZIRCEX to date deployment of advanced for zirconium removal The process feed is composed INL first conducted laboratory reactors to help secure prior to extraction) of previously irradiated fuels scale testing with unirradiated Americas clean energy future.

process recovers highly in the federal complex and zirconium alloy to determine What is HALEU? enriched uranium (HEU) and incorporates three steps: operating parameters for High-assay, low-enriched downblends it to create irradiated fuel samples.

uranium. Uranium containing High-Assay Low-Enriched

• Step 1 - Cladding The parameters were used between 5% and 20% U-235. (zirconium or aluminum) is Uranium (HALEU), defined as to conduct irradiated Why is HALEU needed? uranium containing between removed from nuclear fuel fuel samples tests which Fosters advanced reactor 5% and 20% U-235. by the ZIRCEX dry head- successfully determined development and supports end process. that reaction rates for better nuclear power plant Why ZIRCEX?

• Step 2 - Uranium is irradiated and unirradiated economics. Previous recovery of HEU decontaminated from fuel were comparable. This What are the HALEU sources? from irradiated fuels utilized fission products by a very is important as working Long-term - Enrichment liquid head-end processes compact, modular solvent with unirradiated materials Interim - Downblending that dissolved the entire fuel extraction system. The allows for expeditious testing, current and/or recovered highly element (including cladding enriched uranium (HEU) in the fission products and other resulting in shorter research material) creating a large residues are immobilized and development time.

federal complex. HEU contains 20% or more U-235.

amount of secondary waste. in glass using a small in-can This is avoided as ZIRCEX melt. Currently, INL is using a is a dry head-end process, one-fourth scale pilot facility

• Step 3 - The uranium is which reduces the amount to conduct research and downblended to between of liquid waste by a factor development of the ZIRCEX 5% and 20% U-235, prior of over 1,000. In addition, process on unirradiated to solidification and fuel any residual liquid waste materials which will inform fabrication.

is solidified by vitrification, the integrated hybrid ZIRCEX eliminating liquid waste. process demonstration.

How do we transition from a National Lab Partnership LEU to a HALEU Fuel Cycle? INL is working with DOE Infrastructure updates are national laboratories needed to address safety, integrating their expertise safeguards and security.

Companies making investments in the development of the need a robust HALEU market. hybrid ZIRCEX process.

Advanced reactor developers The partnership supports require HALEU to test their the hybrid process concepts, which in turn create decontamination and the HALEU market. downblending steps. Key This research-and-bridge role partners include:

is a familiar one for DOE. The agency has been instrumental

• Argonne National in advancing technologies for Laboratory - Solvent renewables and other energy Extraction types.

• Pacific Northwest National Laboratory - Waste The hybrid ZIRCEX process for HALEU recovery Treatment

• Oak Ridge National Laboratory - Product For more information Solidification Terry Todd Path Forward (208) 526-3365 INL is currently conducting terry.todd@inl.gov testing of the one-fourth scale ZIRCEX pilot plant, Joseph Campbell while evaluating testing (208) 526-7785 and demonstration of the joseph.campbell@inl.gov hybrid ZIRCEX process using irradiated materials with its gain.inl.gov laboratory partners GAINnuclear GAINnuclear gain_nuclear HALEU fuels will be used in many new advanced reactor designs, some using entirely new fabrication techniques.

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