Fuel Fabrication Capability (FFC) Scrap Recycle Report

Technical Report · Wed Sep 30 00:00:00 EDT 2009

DOI:https://doi.org/10.2172/1131387· OSTI ID:1131387

Youker, Amanda J. ^[1]; Maggos, Laura E. ^[1]; Stepinski, Dominique C. ^[1]; Bakel, Allen J. ^[1]; Vandegrift, George F. ^[1]

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1. Argonne National Laboratory (ANL), Argonne, IL (United States)

The Global Threat Reduction Initiative (GTRI) is currently engaged in the development of an ultra-high density low enriched uranium (LEU) fuel for its high-performance research reactors. The fuel consists of a monolithic uranium-molybdenum alloy containing 10% (weight/weight, or w/w) Mo (U-10Mo) enclosed in Al-6061 cladding with a Zr bonding layer. Significant losses are expected in the manufacturing of the LEU fuel, so a means to recycle uranium from the scrap pieces is needed. Uranium can also be recovered from irradiated U-10Mo fuels. As a result, Argonne National Laboratory (Argonne) is assisting by developing an aqueous processing flowsheet for scrap recovery in the fuel fabrication process and for spent fuel recovery. Experiments are being done to verify predicted dissolution conditions and optimize HNO₃ and HF concentrations for timely dissolution of the fuel without the formation of precipitates, while meeting the requirements needed for further processing by a tributyl phosphate solvent extraction procedure to recover uranium from a nitric acid–based media. Dissolution conditions will be discussed first for the U-10Mo foils, followed by the U-10Mo foils with Al cladding, and finally the U-10Mo foils with Al cladding and a Zr bonding layer. The goal of the dissolution experiments is to test predicted conditions from earlier reports; these conditions were based on literature data and make the necessary adjustments to successfully dissolve the LEU fuels without the formation of precipitates. Final concentrations of all fuel components were determined by Inductively Coupled Plasma Mass Spectrometry (ICP-MS), and the error associated with the values is ±10%.

• Research Organization: Argonne National Laboratory (ANL), Argonne, IL (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Office of Defense Nuclear Nonproliferation
• DOE Contract Number: AC02-06CH11357
• OSTI ID: 1131387
• Report Number(s): ANL/CSE--13/6
• Country of Publication: United States
• Language: ENGLISH