Effect of different glasses in glass bonded zeolite

Conference · Mon May 01 04:00:00 EDT 1995

OSTI ID:61720

Lewis, M A; Ackerman, J P ^[1]; Verma, S ^[2]

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1. Argonne National Lab., IL (United States)
2. Univ. of Illinois, Chicago, IL (United States)

A mineral waste form has been developed for chloride waste salt generated during the pyrochemical treatment of spent nuclear fuel. The waste form consists of salt-occluded zeolite powders bound within a glass matrix. The zeolite contains the salt and immobilizes the fission products. The zeolite powders are hot pressed to form a mechanically stable, durable glass bonded zeolite. Further development of glass bonded zeolite as a waste form requires an understanding of the interaction between the glass and the zeolite. Properties of the glass that enhance binding and durability of the glass bonded zeolite need to be identified. Three types of glass, boroaluminosilicate, soda-lime silicate, and high silica glasses, have a range of properties and are now being investigated. Each glass was hot pressed by itself and with an equal amount of zeolite. MCC-1 leach tests were run on both. Soda-lime silicate and high silica glasses did not give a durable glass bonded zeolite. Boroaluminosilicate glasses rich in alkaline earths did bind the zeolite and gave a durable glass bonded zeolite. Scanning electron micrographs suggest that the boroaluminosilicate glasses wetted the zeolite powders better than the other glasses. Development of the glass bonded zeolite as a waste form for chloride waste salt is continuing.

• Research Organization: Argonne National Lab., IL (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 61720
• Report Number(s): ANL/CMT/CP--84676; CONF-950401--3; ON: DE95011337
• Country of Publication: United States
• Language: English

Related Subjects

05 NUCLEAR FUELS
BOROSILICATE GLASS
CHEMICAL COMPOSITION
GLASS
LEACHING
MINERALS
PERFORMANCE
SPENT FUELS
WASTE FORMS
ZEOLITES