Published April 23, 1984 | Version v1
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Plutonium and americium recovery from spent molten-salt-extraction salts with aluminum-magnesium alloys

Description

Development work was performed to determine the feasibility of removing plutonium and americium from spent molten-salt-extraction (MSE) salts using Al-Mg alloys. If the product buttons from this process are compatible with subsequent aqueous processing, the complex chloride-to-nitrate aqueous conversion step which is presently required for these salts may be eliminated. The optimum alloy composition used to treat spent 8 wt % MSE salts in the past yielded poor phase-disengagement characteristics when applied to 30 mol % salts. After a limited investigation of other alloy compositions in the Al-Mg-Pu-Am system, it was determined that the Al-Pu-Am system could yield a compatible alloy. In this system, experiments were performed to investigate the effects of plutonium loading in the alloy, excess magnesium, age of the spent salt on actinide recovery, phase disengagement, and button homogeneity. Experimental results indicate that 95 percent plutonium recoveries can be attained for fresh salts. Further development is required for backlog salts generated prior to 1981. A homogeneous product alloy, as required for aqueous processing, could not be produced

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 as DE84012560.

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Additional details

Publishing Information

Imprint Pagination
16 p.
Report number
RFP--3614

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
16001642
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Descriptors DEI
ALUMINIUM ALLOYS; AMERICIUM; MAGNESIUM ALLOYS; MOLTEN SALTS; PLUTONIUM; PYROCHEMICAL REPROCESSING; SEPARATION PROCESSES
Descriptors DEC
ACTINIDES; ALLOYS; ELEMENTS; METALS; REPROCESSING; SALTS; TRANSPLUTONIUM ELEMENTS; TRANSURANIUM ELEMENTS