Silicon polymer encapsulation of high level calcine waste for transportation or disposal
Description
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
Availability note (English)
Available from INIS in electronic form; Also available from OSTI as DE00758126; PURL: https://www.osti.gov/servlets/purl/758126-eHY53t/webviewable/
Files
Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 10 p.
- Report number
- INEEL/CON--99-01223
Conference
- Title
- Waste Management 2000 (WM2K) Conference
- Dates
- 27 Feb - 2 Mar 2000
- Place
- Tucson, AZ (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 31051286
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPRESSION STRENGTH; ENCAPSULATION; HIGH-LEVEL RADIOACTIVE WASTES; IMPACT STRENGTH; LEACHING; LOADING RATE; PERFORMANCE TESTING; RADIOACTIVE WASTE DISPOSAL; RADIOACTIVE WASTE PROCESSING; WASTE FORMS; WASTE TRANSPORTATION
- Descriptors DEC
- DISSOLUTION; MANAGEMENT; MATERIALS; MECHANICAL PROPERTIES; PROCESSING; RADIOACTIVE MATERIALS; RADIOACTIVE WASTE MANAGEMENT; RADIOACTIVE WASTES; SEPARATION PROCESSES; TESTING; TRANSPORT; WASTE DISPOSAL; WASTE MANAGEMENT; WASTE PROCESSING; WASTES
Optional Information
- Contract/Grant/Project number
- AC07-99ID13727
- Funding organization
- USDOE Office of Environmental Management (EM) (United States)