Silicon-Polymer Encapsulation of High-Level Calcine Waste for Transportation or Disposal

Technical Report · Sat Jan 01 04:00:00 EST 2000

DOI:https://doi.org/10.2172/762081· OSTI ID:762081

Loomis, G G ^[1]; Miller, C M; Giansiracusa, J A; Kimmel, R; Prewett, S V

---

1. Idaho National Engineering and Environmental Laboratory

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 Engineering and Environmental Laboratory, Idaho Falls, ID (US)
• Sponsoring Organization: USDOE Office of Environmental Management (EM) (US)
• DOE Contract Number: AC07-99ID13727
• OSTI ID: 762081
• Report Number(s): INEEL/EXT-99-01163
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
CALCINE WASTE
COMPRESSIVE STRENGTH TESTING
DISPOSAL
DROP TEST
ENCAPSULATION
HAZARDOUS MATERIALS
HIGH-LEVEL RADIOACTIVE WASTES
LEACHING
MELT TESTING
MELTER
MIXTURES
OXIDIZER TEST
OXIDIZERS
PERFORMANCE TESTING
POLYMERS
POLYSILOXANE
RADIOACTIVE
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTE PROCESSING
SILICON
SILICON-POLYMER ENCAPSULATION
TOXICITY
TOXICITY CHARACTERISTIC LEACHING PROCEDURE (TCLP)
TRANSPORTATION
WASTE FORM
WASTE FORMS