The density of nitric acid solutions of uranium and uranium-aluminium alloys

✍ Scribed by H.H.Ph. Moeken

• Book ID: 104103909
• Publisher: Elsevier Science
• Year: 1969
• Tongue: English
• Weight: 312 KB
• Volume: 44
• Category: Article
• ISSN: 0003-2670
• DOI: 10.1016/s0003-2670(01)81757-8

✦ Synopsis

The density of nitric acid solutions of uranium and uranium-aluminium alloys

The solution obtained after dissolution in nitric acid of uranium fuel in the chemical reprocessing of irradiated reactor fuel of low enrichment is ca. 1.0-1.5 M in uranyl nitrate and 2.5-3.5 M in nitric acid. Uranium fuel of high enrichment, made of aluminium-uranium alloy, yields a solution which is either 1-2 M in basic aluminium nitrate and x-2.5 M in hydroxyl, or I-_, 3 M in aluminium nitrate and 0.5-1.5 M in nitric acid. The uranium content of these solutions is up to 4 g/l or 0.02 M.