Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Purification of U from U-10Mo scrap generated during the fabrication of high performance research reactor fuel

Journal Article · · Separation Science and Technology
 [1];  [2]
  1. Savannah River National Laboratory (SRNL), Aiken, SC (United States)
  2. Argonne National Laboratory (ANL), Argonne, IL (United States)

A low enriched U-Mo alloy fuel is under development to replace highly enriched U fuels currently used in United States high performance research reactors. The alloy casting and fuel fabrication processes will generate scrap streams containing low enriched U (LEU) which must be recovered. Solvent extraction processes were designed using the Argonne Model for Universal Solvent Extraction (AMUSE) to purify solutions containing 20 and 50 g/L U. The feed for the solvent extraction processes was prepared from solutions generated from the dissolution of U-10Mo-Zr foils and U-10Mo-Zr-Al mini-plates. The U purification processes were demonstrated using two, 16-stage banks of miniature mixer-settlers. The solvent extraction experiments demonstrated that all design objectives for the U purification processes could be met. The U recovery in the product stream for each flowsheet was ≥99.9%. The flowsheet demonstrations also showed that the purity of the U Product will meet the requirements of the ASTM International C1462-21 specification for LEU metal enriched to less than 20% 235U. In conclusion, the AMUSE modeling for both flowsheet demonstrations was validated by comparing predicted and measured concentrations of U, Mo, and Zr in the exit streams and stage samples at steady-state conditions in the mixer-settlers.

Research Organization:
Savannah River National Laboratory (SRNL), Aiken, SC (United States)
Sponsoring Organization:
USDOE Office of Environmental Management (EM); USDOE National Nuclear Security Administration (NNSA)
Grant/Contract Number:
89303321CEM000080
OSTI ID:
2557438
Report Number(s):
SRNL--STI-2024-00070
Journal Information:
Separation Science and Technology, Journal Name: Separation Science and Technology; ISSN 0149-6395
Publisher:
Taylor & FrancisCopyright Statement
Country of Publication:
United States
Language:
English

References (1)

The Chemistry of the Actinide and Transactinide Elements book January 2006

Similar Records

Dissolution Flowsheet for U-10Mo Scrap Generated from the Fabrication of High Performance Research Reactor Fuel
Technical Report · Sun Sep 01 00:00:00 EDT 2019 · OSTI ID:1569636

Pyrochemical Recovery of Uranium from Monolithic U-10Mo Fuel Scrap
Technical Report · Fri Feb 27 23:00:00 EST 2009 · OSTI ID:1131398

Fuel Fabrication Capability (FFC) Scrap Recycle Report
Technical Report · Wed Sep 30 00:00:00 EDT 2009 · OSTI ID:1131387