Mixed Waste Salt Encapsulation Using Polysiloxane - Final Report

Technical Report · Sat Nov 01 04:00:00 EST 1997

DOI:https://doi.org/10.2172/5724· OSTI ID:5724

Miller, C M ^[1]; Loomis, G G; Prewett, S W

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1. Lockheed Martin Idaho Technologies Company

A proof-of-concept experimental study was performed to investigate the use of Orbit Technologies polysiloxane grouting material for encapsulation of U.S. Department of Energy mixed waste salts leading to a final waste form for disposal. Evaporator pond salt residues and other salt-like material contaminated with both radioactive isotopes and hazardous components are ubiquitous in the DOE complex and may exceed 250,000,000 kg of material. Current treatment involves mixing low waste percentages (less than 10% by mass salt) with cement or costly thermal treatment followed by cementation to the ash residue. The proposed technology involves simple mixing of the granular salt material (with relatively high waste loadings-greater than 50%) in a polysiloxane-based system that polymerizes to form a silicon-based polymer material. This study involved a mixing study to determine optimum waste loadings and compressive strengths of the resultant monoliths. Following the mixing study, durability testing was performed on promising waste forms. Leaching studies including the accelerated leach test and the toxicity characteristic leaching procedure were also performed on a high nitrate salt waste form. In addition to this testing, the waste form was examined by scanning electron microscope. Preliminary cost estimates for applying this technology to the DOE complex mixed waste salt problem is also given.

• Research Organization: Idaho National Engineering and Environmental Lab., Idaho Falls, ID (US)
• Sponsoring Organization: USDOE Office of Environmental Management (EM) (US)
• DOE Contract Number: AC07-94ID13223
• OSTI ID: 5724
• Report Number(s): INEEL/EXT-97-01234
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ACCELERATED LEACH TEST
CEMENTATION
COMPRESSION STRENGTH
COMPRESSIVE STRENGTHS
CORROSION RESISTANCE
DISPOSAL
ENCAPSULATION
FINAL WASTE FORM
GROUTING
HAZARDOUS COMPONENTS
LEACHING
LOADING RATE
MIXED WASTE SALTS
MONOLITHS
OPTIMUM WASTE LOADINGS
ORGANIC POLYMERS
POLYSILOXANE GROUTING MATERIAL
RADIOACTIVE ISOTOPES
RADIOACTIVE WASTE DISPOSAL
SETTLING PONDS
SILICON-BASED POLYMER MATERIAL
SILOXANES
THERMAL TREATMENT
TOXICITY
TOXICITY CHARACTERISTIC LEACHING PROCEDURE
WASTE FORMS