Silicon polymer encapsulation of high level calcine waste for transportation or disposal
Conference
·
OSTI ID:758126
- Idaho National Engineering and Environmental Laboratory
Engineers at the Idaho National Engineering and Environmental Laboratory (INEEL) are investigating the use of a proprietary silicon-polymer to encapsulate high-level calcine waste stored at the INEEL's Idaho Nuclear Technology and Engineering Center (INTEC). The silicon-polymer-encapsulated waste may be suitable for direct disposal at a radioactive waste disposal facility or for transport to an offsite melter for further processing. In connection with silicon-polymer encapsulation, the University of Akron, under special arrangement with Orbit Technologies, the originator of the Polymer Encapsulation Technology (PET), has studied a simulated waste material from INTEC called pilot-scale calcine that contains hazardous materials but no radioactive isotopes. In this study, Toxicity Characteristic Leaching Procedure (TCLP) and Materials Characterization Center Test 1P were performed to test the waste form for disposal. In addition, a maximum waste loading was established for transporting the calcine waste at INTEC to an offsite melter. For this maximum waste loading, compressive strength testing, 10-m drop testing, melt testing, and a Department of Transportation (DOT) oxidizer test were performed.
- 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:
- 758126
- Report Number(s):
- INEEL/CON-99-01223
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
CALCINE
COMPRESSION STRENGTH
COMPRESSIVE STRENGTH
DISPOSAL FACILITY
DROP TESTING
ENCAPSULATE
ENCAPSULATION
HAZARDOUS MATERIALS
HIGH-LEVEL RADIOACTIVE WASTES
IMPACT STRENGTH
LEACHING
LOADING RATE
MELT TESTING
OXIDIZER TEST
PERFORMANCE TESTING
RADIOACTIVE WASTE DISPOSAL
SILICON-POLYMER
TOXICITY CHARACTERISTIC LEACHING PROCEDURE (TCLP)
WASTE FORMS
WASTE LOADING
WASTE TRANSPORTATION
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
CALCINE
COMPRESSION STRENGTH
COMPRESSIVE STRENGTH
DISPOSAL FACILITY
DROP TESTING
ENCAPSULATE
ENCAPSULATION
HAZARDOUS MATERIALS
HIGH-LEVEL RADIOACTIVE WASTES
IMPACT STRENGTH
LEACHING
LOADING RATE
MELT TESTING
OXIDIZER TEST
PERFORMANCE TESTING
RADIOACTIVE WASTE DISPOSAL
SILICON-POLYMER
TOXICITY CHARACTERISTIC LEACHING PROCEDURE (TCLP)
WASTE FORMS
WASTE LOADING
WASTE TRANSPORTATION