Dissolving uranium oxide--aluminum fuel

Technical Report · Thu Nov 01 00:00:00 EST 1973

DOI:https://doi.org/10.2172/4367242· OSTI ID:4367242

Perkins, W C

The dissolution of aluminum-clad uranium oxide-aluminum fuel was studied to provide basic data for dissolving this type of enriched uranium fuel at the Savannah River Plant. The studies also included the dissolution of a similar material prepared from scrap uranium oxides that were to be recycled through the solvent extraction process. The dissolving behavior of uranium oxide-aluminum core material is similar to that of U-Al alloy. Dissolving rates are rapid in HNO/sub 3/-Hg(NO/sub 3/)/sub 2/ solutions. Irradiation reduce s the dissolving rate and increases mechanical strength. A dissolution model for use in nuclear safety analyses is developed, . based on the observed dissolving characteristics. (auth)

• Research Organization: Du Pont de Nemours (E.I.) and Co., Aiken, SC (United States). Savannah River Lab.
• DOE Contract Number: AT(07-2)-1
• NSA Number: NSA-29-009999
• OSTI ID: 4367242
• Report Number(s): DP-1337
• Resource Relation: Other Information: Orig. Receipt Date: 30-JUN-74
• Country of Publication: United States
• Language: English

Related Subjects

N40450* -Chemistry-Radiochemistry & Nuclear Chemistry- Reactor Fuel Processing
*ALUMINIUM- DISSOLUTION
*SPENT FUELS- REPROCESSING
*U3O8- DISSOLUTION
*URANIUM OXIDES U3O8- DISSOLUTION
CHEMICAL RADIATION EFFECTS
ENRICHED URANIUM
IRRADIATION
MECHANICAL PROPERTIES
MERCURY NITRATES
NITRIC ACID URANIUM OXIDES U3O8