Differential leaching studies: HTGR fuel reprocessing development

Technical Report · Fri Aug 01 00:00:00 EDT 1975

DOI:https://doi.org/10.2172/4139405· OSTI ID:4139405

Wilbourn, R. G.

Differential leaching is defined as the ability to preferentially dissolve uranium from fissile particles rather than the bred uranium contained in fertile particles during HTGR fuel reprocessing. Thus, differential leaching offers a potential separation of parasitic $sup 236$U from bred $sup 233$U on a basis other than the difference between fissile and fertile particle size or density. Specifically, the solubility differences of U$sub 3$$O$$sub 8$, ThO$sub 2$, and mixed oxides in nitric acid form the basis for differential leaching. The application of differential leaching in various reprocessing flow sheets is considered. Data from previous and current investigations at General Atomic Company are presented. Some degree of separation of fertile particle $sup 233$U from fissile particle $sup 235$U and $sup 236$U (separation factors 20 to 100) was obtained by treating simulated ash with nitric acid concentrations as low as 1 M. The success of any differential leaching flow sheet is strongly dependent on the irradiation exposure, Th/U ratio, fabrication technique, etc., of the material being leached. (auth)

• Research Organization: General Atomics, San Diego, CA (United States)
• DOE Contract Number: E(04-3)-167
• NSA Number: NSA-33-008998
• OSTI ID: 4139405
• Report Number(s): GA-A-13552
• Resource Relation: Other Information: Orig. Receipt Date: 30-JUN-76
• Country of Publication: United States
• Language: English

Related Subjects

N40450* -Chemistry-Radiochemistry & Nuclear Chemistry- Reactor Fuel Processing
050800* -Nuclear Fuels-Spent Fuels Reprocessing
*FUEL PARTICLES- SORTING
*SPENT FUELS- REPROCESSING
FLOWSHEETS
HTGR TYPE REACTORS
LEACHING
NITRIC ACID
SEPARATION PROCESSES
THORIUM OXIDES
URANIUM 233
URANIUM 236
URANIUM OXIDES U3O8