High-Level Waste Vitrification Facility Feasibility Study
- Lockheed Martin Idaho Technologies Company
A ''Settlement Agreement'' between the Department of Energy and the State of Idaho mandates that all radioactive high-level waste now stored at the Idaho Nuclear Technology and Engineering Center will be treated so that it is ready to be moved out of Idaho for disposal by a compliance date of 2035. This report investigates vitrification treatment of the high-level waste in a High-Level Waste Vitrification Facility based on the assumption that no more New Waste Calcining Facility campaigns will be conducted after June 2000. Under this option, the sodium-bearing waste remaining in the Idaho Nuclear Technology and Engineering Center Tank Farm, and newly generated liquid waste produced between now and the start of 2013, will be processed using a different option, such as a Cesium Ion Exchange Facility. The cesium-saturated waste from this other option will be sent to the Calcine Solids Storage Facilities to be mixed with existing calcine. The calcine and cesium-saturated waste will be processed in the High-Level Waste Vitrification Facility by the end of calendar year 2035. In addition, the High-Level Waste Vitrification Facility will process all newly-generated liquid waste produced between 2013 and the end of 2035. Vitrification of this waste is an acceptable treatment method for complying with the Settlement Agreement. This method involves vitrifying the waste and pouring it into stainless-steel canisters that will be ready for shipment out of Idaho to a disposal facility by 2035. These canisters will be stored at the Idaho National Engineering and Environmental Laboratory until they are sent to a national geologic repository. The operating period for vitrification treatment will be from the end of 2015 through 2035.
- 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:
- 11011
- Report Number(s):
- INEEL/EXT-99-00792
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
CALCINE SOLIDS STORAGE
CESIUM ION EXCHANGE
CESIUM-SATURATED WASTE
DISPOSAL
FEASIBILITY STUDIES
HIGH-LEVEL RADIOACTIVE WASTE
HIGH-LEVEL RADIOACTIVE WASTES
IDAHO NATIONAL ENGINEERING LABORATORY
IDAHO NUCLEAR TECHNOLOGY AND ENGINEERING CENTER
LIQUID WASTES
NATIONAL GEOLOGICAL REPOSITORY
RADIOACTIVE WASTE FACILITIES
RADIOACTIVE WASTE PROCESSING
RADIOACTIVE WASTE STORAGE
SODIUM-BEARING WASTE
VITRIFICATION
CALCINE SOLIDS STORAGE
CESIUM ION EXCHANGE
CESIUM-SATURATED WASTE
DISPOSAL
FEASIBILITY STUDIES
HIGH-LEVEL RADIOACTIVE WASTE
HIGH-LEVEL RADIOACTIVE WASTES
IDAHO NATIONAL ENGINEERING LABORATORY
IDAHO NUCLEAR TECHNOLOGY AND ENGINEERING CENTER
LIQUID WASTES
NATIONAL GEOLOGICAL REPOSITORY
RADIOACTIVE WASTE FACILITIES
RADIOACTIVE WASTE PROCESSING
RADIOACTIVE WASTE STORAGE
SODIUM-BEARING WASTE
VITRIFICATION