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Recovery of Uranium from Highly Irradiated Reactor Fuel by a Fused-Salt Fluoride-Volatility Process

Conference ·
OSTI ID:4317497
Volatility processing is a promising new nonaqueous method for recovering uranium from heterogeneous reactor fuels containing zirconium and from molten fluoride fuels. it is potentially applicable to other types of reactor fuels not amenable to aqueous dissolution and subsequent solvent extraction processing. Amond the attractive features of the fused salt-fluoride volatility process are the small volume of the fission product waste, which is in solid form; the form of product, UF6; and virtual elimination of the need for criticality control. the main disadvantages are the high temperatures used and the high equipment corrosion. The paper discusses the processes under development.
Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC)
DOE Contract Number:
W-7405-ENG-26
NSA Number:
NSA-12-014690
OSTI ID:
4317497
Report Number(s):
A/CONF.15/P/535
Country of Publication:
United States
Language:
English