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Title: Synthesis of Uranium Trichloride for the Pyrometallurgical Processing of Used Nuclear Fuel

The pyroprocessing of used nuclear fuel via electrorefining requires the continued addition of uranium trichloride to sustain operations. Uranium trichloride is utilized as an oxidant in the system to allow separation of uranium metal from the minor actinides and fission products. The inventory of uranium trichloride had diminished to a point that production was necessary to continue electrorefiner operations. Following initial experimentation, cupric chloride was chosen as a reactant with uranium metal to synthesize uranium trichloride. Despite the variability in equipment and charge characteristics, uranium trichloride was produced in sufficient quantities to maintain operations in the electrorefiner. The results and conclusions from several experiments are presented along with a set of optimized operating conditions for the synthesis of uranium trichloride.
Authors:
; ;
Publication Date:
OSTI Identifier:
1045491
Report Number(s):
INL/CON-10-20111
TRN: US1203624
DOE Contract Number:
DE-AC07-05ID14517
Resource Type:
Conference
Resource Relation:
Conference: Fray International Symposium on Molten Salts and Ionic Liquids 2011,Cancun, Mexico,11/27/2011,12/01/2011
Research Org:
Idaho National Laboratory (INL)
Sponsoring Org:
DOE - NE
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; ACTINIDES; CHLORIDES; ELECTROREFINING; FISSION PRODUCTS; MOLTEN SALTS; NUCLEAR FUELS; OXIDIZERS; PROCESSING; PRODUCTION; SYNTHESIS; URANIUM; SPENT FUELS; Pyrometallurgical Processing; Uranium Trichloride