Pyrochemical Recovery of Uranium from Monolithic U-10Mo Fuel Scrap

Technical Report · Fri Feb 27 23:00:00 EST 2009

DOI:https://doi.org/10.2172/1131398· OSTI ID:1131398

Figueroa, J. ^[1]; Williamson, M. A. ^[1]

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

This report provides a description of a pyrochemical processing system designed to recover low enriched uranium from uranium 10 wt% molybdenum alloy (U-10Mo) scrap that is bonded to aluminum cladding. Approximately 44 wt% (2327 kg) of the initial U-10Mo fuel meat used to create fuel foils for the five U.S. high-performance research reactors will be recycled annually (Wachs et al. 2008). The U-10Mo recycle stream is a mixture of materials including casting scrap from the uranium down-blending process, shearing losses from foil sizing, rejected fuel elements, and material from hold-up in crucibles and other contaminated equipment. A description of the process chemistry, processing equipment including size, and approximate footprint of the proposed scrap recovery line is presented. In addition, a mass balance flowsheet that identifies and quantifies product streams, waste streams, and process reagent requirements is provided for the proposed recycle process.

• 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: 1131398
• Report Number(s): ANL/CSE--13/14
• Country of Publication: United States
• Language: ENGLISH