Molten salt extraction (MSE) of americium from plutonium metal in CaCl{sub 2}-KCl-PuCl{sub 3} and CaCl{sub 2}-PuCl{sub 3} salt systems

Thesis/Dissertation · Thu Jun 11 00:00:00 EDT 1992

OSTI ID:10188175

Dodson, K E

Molten salt extraction (MSE) of americium-241 from reactor-grade plutonium has been developed using plutonium trichloride salt in stationary furnaces. Batch runs with oxidized and oxide-free metal have been conducted at temperature ranges between 750 and 945C, and plutonium trichloride concentrations from one to one hundred mole percent. Salt-to-metal ratios of 0.10, 0.15, and 0 30 were examined. The solvent salt was either eutectic 74 mole percent CaCl{sub 2}{endash}26 mole percent KCl or pure CaCl{sub 2}. Evidence of trivalent product americium, and effects of temperature, salt-to-metal ratio, and oxide contamination on the americium extraction efficiency are given. 24 refs, 20 figs, 13 tabs.

• Research Organization: Lawrence Livermore National Lab., CA (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: W-7405-ENG-48
• OSTI ID: 10188175
• Report Number(s): UCRL-LR-110870; ON: DE93001623
• Resource Relation: Other Information: DN: Thesis. Submitted to Univ. of California, Davis.; TH: Thesis (M.S.); PBD: 11 Jun 1992
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEAR CHEMISTRY
AMERICIUM 241
EXTRACTION
PLUTONIUM
PLUTONIUM CHLORIDES
TEMPERATURE RANGE 1000-4000 K
MOLTEN SALTS
PYROCHEMICAL REPROCESSING
CALCIUM CHLORIDES
POTASSIUM CHLORIDES
050800
400703
SPENT FUELS REPROCESSING
RADIOISOTOPE PRODUCTION