Vitrification of low level and mixed (radioactive and hazardous) wastes: Lessons learned from high level waste vitrification

Conference · Fri Jul 01 00:00:00 EDT 1994

OSTI ID:10163565

Jantzen, C M

Borosilicate glasses will be used in the USA and in Europe immobilize radioactive high level liquid wastes (HLLW) for ultimate geologic disposal. Simultaneously, tehnologies are being developed by the US Department of Energy`s (DOE) Nuclear Facility sites to immobilize low-level and mixed (radioactive and hazardous) wastes (LLMW) in durable glass formulations for permanent disposal or long-term storage. Vitrification of LLMW achieves large volume reductions (86--97 %) which minimize the associated long-term storage costs. Vitrification of LLMW also ensures that mixed wastes are stabilized to the highest level reasonably possible, e.g. equivalent to HLLW, in order to meet both current and future regulatory waste disposal specifications The tehnologies being developed for vitrification of LLMW rely heavily on the technologies developed for HLLW and the lessons learned about process and product control.

• Research Organization: Westinghouse Savannah River Co., Aiken, SC (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC09-89SR18035
• OSTI ID: 10163565
• Report Number(s): WSRC-MS-94-0334; CONF-940815-50; ON: DE94014649; TRN: 94:013669
• Resource Relation: Conference: SPECTRUM `94: international nuclear and hazardous waste management conference,Atlanta, GA (United States),14-18 Aug 1994; Other Information: PBD: [1994]
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
SAVANNAH RIVER PLANT
RADIOACTIVE WASTE PROCESSING
LOW-LEVEL RADIOACTIVE WASTES
VITRIFICATION
HIGH-LEVEL RADIOACTIVE WASTES
GLASS
RADIOACTIVE WASTE DISPOSAL
STABILITY
VISCOSITY
THERMODYNAMICS
SOLUBILITY
BOROSILICATE GLASS
052001
WASTE PROCESSING