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Three Mile Island zeolite vitrification demonstration program

Journal Article · · AIChE Symp. Ser.; (United States)
OSTI ID:5150868
; ;

This paper presents a brief overview of the Three Mile Island (TMI) zeolite vitrification program. The formulation of a glass suitable for immobilizing submerged demineralizer system (SDS) zeolites is discussed. A feed system that was developed to feed zeolites to the in-can melter is described. The in-can melting process and the government-owned facilities in which the demonstrations will take place are examined. The schedule for completing the program activities is outlined. The specific objectives of the program are: to establish that the vitrification of zeolites is a feasible method of immobilizing high-activity level special wastes, to characterize the vitrified waste form, and to provide a radioactive waste form for further analysis and for possible disposal demonstrations.

Research Organization:
Pacific Northwest Laboratory, Richland, Washington
OSTI ID:
5150868
Journal Information:
AIChE Symp. Ser.; (United States), Journal Name: AIChE Symp. Ser.; (United States) Vol. 78:213; ISSN ACSSC
Country of Publication:
United States
Language:
English

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ABSORPTION
ALKALI METALS
ALKALINE EARTH METALS
CESIUM
CLEANING
DECONTAMINATION
DEMINERALIZERS
DEMONSTRATION PROGRAMS
ELEMENTS
ENRICHED URANIUM REACTORS
EQUIPMENT
FILTRATION
GLASS
HOT CELLS
INORGANIC ION EXCHANGERS
ION EXCHANGE
ION EXCHANGE MATERIALS
LABORATORY EQUIPMENT
MANAGEMENT
MATERIALS
MATERIALS HANDLING EQUIPMENT
MELTING
METALS
MINERALS
PHASE TRANSFORMATIONS
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PWR TYPE REACTORS
RADIOACTIVE WASTE MANAGEMENT
RADIOACTIVE WASTE PROCESSING
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REMOTE HANDLING EQUIPMENT
REMOTE VIEWING EQUIPMENT
SEPARATION PROCESSES
SOLIDIFICATION
STRONTIUM
TECHNOLOGY UTILIZATION
THERMAL REACTORS
THREE MILE ISLAND-2 REACTOR
VITRIFICATION
WASTE MANAGEMENT
WASTE PROCESSING
WATER COOLED REACTORS
WATER MODERATED REACTORS
WATER TREATMENT
ZEOLITES