Comparison of cation exchange resins for recovering americium and plutonium from chloride wastes

Technical Report · Wed Apr 25 00:00:00 EST 1984

OSTI ID:6839769

Silva, R A; Smith, C M; Navratil, J D; Thompson, G H

Macroreticular and microreticular cation exchange resins were compared for their capability of recovering americium and plutonium from solutions of calcium, magnesium, potassium, and sodium chlorides. Americium and plutonium breakthrough capacity and elution behavior of the resins were determined. Of the resins tested, Dowex MSC-1 was selected as the most efficient because of its favorable capacity and excellent elution behavior. Actinide eluting agents were also studied. More concentrated (9.0M) nitric acid was found to elute plutonium faster than 7.0M HNO/sub 3/ used previously, while 7.0M HNO/sub 3/-0.1M NANO/sub 2/ eluted americium fastest.

• Research Organization: Rockwell International Corp., Golden, CO (USA). Rocky Flats Plant
• DOE Contract Number: AC04-76DP03533
• OSTI ID: 6839769
• Report Number(s): RFP-3563; ON: DE84012144
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
AMERICIUM
RECOVERY
PLUTONIUM
CALCIUM CHLORIDES
CATIONS
CHLORIDES
ION EXCHANGE
MAGNESIUM CHLORIDES
MOLTEN SALTS
POTASSIUM CHLORIDES
RESINS
SODIUM CHLORIDES
ACTINIDES
ALKALI METAL COMPOUNDS
ALKALINE EARTH METAL COMPOUNDS
CALCIUM COMPOUNDS
CALCIUM HALIDES
CHARGED PARTICLES
CHLORINE COMPOUNDS
ELEMENTS
HALIDES
HALOGEN COMPOUNDS
IONS
MAGNESIUM COMPOUNDS
METALS
ORGANIC COMPOUNDS
ORGANIC POLYMERS
PETROCHEMICALS
PETROLEUM PRODUCTS
POLYMERS
POTASSIUM COMPOUNDS
SALTS
SODIUM COMPOUNDS
TRANSPLUTONIUM ELEMENTS
TRANSURANIUM ELEMENTS
050800* - Nuclear Fuels- Spent Fuels Reprocessing