Tentative grind--leach process for Rover fuels

Technical Report · Tue Jan 13 04:00:00 EST 1959

DOI:https://doi.org/10.2172/4407160· OSTI ID:4407160

Fitch, A Jr; Ferris, L M

Declassified 24 Sep 1973. A tentative flowsheet is presented for the recovery of uranium from prototype Rover fuel by leaching with boiling 15.8 M HNO/ sub 3/. The effects of uranium content of the fuel, nitric acid concentration, and particle size on the efficiency of leaching were partially determined. For fuel containing more than 100 mg U per cc 15 wt%), 99.3% of the uranium was leached in 6 hr with 8 M HNO/sub 3/ when the fuel was ground to -16 mesh. However, only 98.6% of the uranium was leached from fuel -containing 35 mg U per cc (1.8 wt%) in 6 hr with 15.8 M HNO/sub 3/ when the fuel was ground to -16 mesh. The use of 8 M HNO/sub 3/ on fuel of the latter composition resulted in even lower uranium recoveries. (auth)

• Research Organization: Oak Ridge National Lab., Tenn. (USA)
• DOE Contract Number: W-7405-ENG-26
• NSA Number: NSA-29-004984
• OSTI ID: 4407160
• Report Number(s): ORNL--2640
• Country of Publication: United States
• Language: English

Related Subjects

*SPENT FUELS-- REPROCESSING
*URANIUM-- SEPARATION PROCESSES
FLOWSHEETS
GRINDING
LEACHING
N40450* --Chemistry--Radiochemistry & Nuclear Chemistry-- Reactor Fuel Processing
NESDPS Office of Nuclear Energy Space and Defense Power Systems
NITRIC ACID
PARTICLE SIZE
QUANTITY RATIO
ROVER REACTORS