Leach resistance properties and release processes for salt-occluded zeolite A
Conference
·
OSTI ID:10117912
The pyrometallurgical processing of spent fuel from the Integral Fast Reactor (IFR) results in a waste of LiCl-KCl-NaCl salt containing approximately 10 wt% fission products, primarily CsCl and SrCl{sub 2}. For disposal, this waste must be immobilized in a form that it is leach resistant. A salt-occluded zeolite has been identified as a potential waste form for the salt. Its leach resistance properties were investigated using powdered samples. The results were that strontium was not released and cesium had a low release, 0.056 g/m{sup 2} for the 56 day leach test. The initial release (within 7 days) of alkali metal cations was rapid and subsequent releases were much smaller. The releases of aluminum and silicon were 0.036 and 0.028 g/m{sup 2}, respectively, and were constant. Neither alkali metal cation hydrolysis nor exchange between cations in the leachate and those in the zeolite was significant. Only sodium release followed t{sup 0.5} kinetics. Selected dissolution of the occluded salt was the primary release process. These results confirm that salt-occluded zeolite has promise as the waste form for IFR pyroprocess salt.
- Research Organization:
- Argonne National Lab., IL (United States). Chemical Technology Div.
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 10117912
- Report Number(s):
- ANL/CMT/CP--77755; CONF-921101--30; ON: DE93005573
- Country of Publication:
- United States
- Language:
- English
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Leach resistance properties and release processes for salt-occluded zeolite A
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Journal Article
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OSTI ID:5535109
Related Subjects
050800
052000
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500
36 MATERIALS SCIENCE
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CORROSION, EROSION, AND DEGRADATION
FISSION PRODUCTS
FUEL CYCLE
IFR REACTOR
LEACHING
POWER REACTORS
BREEDING
PYROCHEMICAL REPROCESSING
SALTS
SPENT FUELS REPROCESSING
WASTE FORMS
WASTE MANAGEMENT
ZEOLITES
052000
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500
36 MATERIALS SCIENCE
360604
CORROSION, EROSION, AND DEGRADATION
FISSION PRODUCTS
FUEL CYCLE
IFR REACTOR
LEACHING
POWER REACTORS
BREEDING
PYROCHEMICAL REPROCESSING
SALTS
SPENT FUELS REPROCESSING
WASTE FORMS
WASTE MANAGEMENT
ZEOLITES