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Title: ELECTROLYTIC DISSOLUTION OF NUCLEAR FUELS. PART I. ZIRCONIUM IN HCl- METHANOL

Technical Report ·
DOI:https://doi.org/10.2172/4796884· OSTI ID:4796884

The electrolytic dissolution of zirconium in HCl-methanol was studied as a function of potential, solution composition, and temperature. The dissolution is characterized by two regions. At high potentials the zirconium is electropolished and complete dissolution is achieved. At low potentials the current is an exponential function of the potential (Tafel behavior). In this region a small amount of finely divided alpha -zirconium which is insoluble in HCl-methanol separates from the bulk metal. The energy of activation for the corrosion reaction (0.0 volt) is 16.5 kcal/mole; in the electropolishing region (1.0 volt) the activation energy is 7.7 kcal/mole. A broad solvent capability for metallic reactor fuels is offered by the HCl-methanol medium since, in addition to zirconium, stainless steel is also dissolved electrolytically while uranium and aluminum dissolve chemically. Other process implications are discussed. (auth)

Research Organization:
Phillips Petroleum Co. Atomic Energy Div., Idaho Falls, Idaho
Sponsoring Organization:
US Atomic Energy Commission (AEC)
DOE Contract Number:
AT(10-1)-205
NSA Number:
NSA-16-013126
OSTI ID:
4796884
Report Number(s):
IDO-14573
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-62
Country of Publication:
United States
Language:
English