The effects of zirconium on the dissolution rate of thoria in nitric-hydrofluoric acid solutions

Journal Article · Tue Mar 01 00:00:00 EST 1983 · Nucl. Technol.; (United States)

OSTI ID:5451364

Tallent, O K; Buxton, S R; Campbell, D O; Mailen, J C

Dissolution tests using ThO/sub 2/ microspheres, ThO/sub 2/ pellets, and Zircaloy tubing were performed to establish conditions that can be used for the selective dissolution of thoria from Zircaloy cladding. Although additional work is needed in several areas, the following conditions are tentatively recommended for use in process demonstration tests: 0.02 to 0.04 M HF in refluxing 8 to 12 M HNO/sub 3/ with sufficient Al/sup 3 +/, or (preferably) Zr/sup 4 +/, added to prevent major corrosion of the stainless steel dissolver vessel. If Zr/sup 4 +/ is used, the concentration required is approximately the same molarity as the fluoride concentration.

• Research Organization: Oak Ridge National Laboratory, Chemical Technology Division, P.O. Box X, Oak Ridge, Tennessee 37830
• OSTI ID: 5451364
• Journal Information: Nucl. Technol.; (United States), Vol. 60:3
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
THORIUM OXIDES
DISSOLUTION
ZIRCALOY
SOLUBILITY
FUEL PELLETS
HYDROFLUORIC ACID
MICROSPHERES
NITRIC ACID
STAINLESS STEELS
TUBES
ACTINIDE COMPOUNDS
ALLOYS
CHALCOGENIDES
CHROMIUM ALLOYS
CORROSION RESISTANT ALLOYS
HYDROGEN COMPOUNDS
INORGANIC ACIDS
IRON ALLOYS
IRON BASE ALLOYS
OXIDES
OXYGEN COMPOUNDS
PELLETS
STEELS
THORIUM COMPOUNDS
TIN ALLOYS
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
050800* - Nuclear Fuels- Spent Fuels Reprocessing