Polysiloxane Encapsulation of High Level Calcine Waste for Transportation or Disposal

Technical Report · Wed Mar 01 00:00:00 EST 2000

DOI:https://doi.org/10.2172/911488· OSTI ID:911488

Loomis, Guy George

This report presents the results of an experimental study investigating the potential uses for silicon-polymer encapsulation of High Level Calcine Waste currently stored within the Idaho Nuclear Technology and Engineering Center (INTEC) at the Idaho National Engineering and Environmental Laboratory (INEEL). The study investigated two different applications of silicon polymer encapsulation. One application uses silicon polymer to produce a waste form suitable for disposal at a High Level Radioactive Waste Disposal Facility directly, and the other application encapsulates the calcine material for transportation to an offsite melter for further processing. A simulated waste material from INTEC, called pilot scale calcine, which contained hazardous materials but no radioactive isotopes was used for the study, which was performed at the University of Akron under special arrangement with Orbit Technologies, the originators of the silicon polymer process called Polymer Encapsulation Technology (PET). This document first discusses the PET process, followed by a presentation of past studies involving PET applications to waste problems. Next, the results of an experimental study are presented on encapsulation of the INTEC calcine waste as it applies to transportation or disposal of calcine waste. Results relating to long-term disposal include: 1) a characterization of the pilot calcine waste; 2) Toxicity Characteristic Leaching Procedure (TCLP) testing of an optimum mixture of pilot calcine, polysiloxane and special additives; and, 3) Material Characterization Center testing MCC-1P evaluation of the optimum waste form. Results relating to transportation of the calcine material for a mixture of maximum waste loading include: compressive strength testing, 10-m drop test, melt testing, and a Department of Transportation (DOT) oxidizer test.

• Research Organization: Idaho National Lab. (INL), Idaho Falls, ID (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: DE-AC07-99ID-13727
• OSTI ID: 911488
• Report Number(s): INEEL/EXT-99-01163; TRN: US0704588
• Country of Publication: United States
• Language: English

Related Subjects

12 - MGMT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
54 - ENVIRONMENTAL SCIENCES
ADDITIVES
ENCAPSULATION
HAZARDOUS MATERIALS
LEACHING
MIXTURES
OXIDIZERS
POLYMERS
PROCESSING
RADIOACTIVE WASTE DISPOSAL
SILICON
TESTING
TOXICITY
US DOT
WASTE FORMS
WASTES
calcine waste
compressive strength testing
disposal
drop test
hazardous materials
melt testing
melter
oxidizer test
polysiloxane
radioactive
silicon-polymer encapsulation
Toxicity Characteristic Leaching Procedure (TCLP)
transportation
waste form