Technical summary: Nuclear Waste Vitrification Project

Technical Report · Tue May 01 00:00:00 EDT 1979

DOI:https://doi.org/10.2172/6086723· OSTI ID:6086723

Wheelwright, E J; Bjorklund, W J; Browne, L M; Bryan, G H; Holton, L K; Irish, E R; Siemens, D H

Six PWR fuel assemblies, containing 2.3 metric tons uranium from Point Beach, have been processed by a conventional Purex-type process. U and other chemicals were added to the dilute HLLW, and the waste was then vitrified to produce two canisters of glass. The on-stream efficiency of the waste preparation facility exceeded 90% for the first 3 weeks; the overall average was 62%. The only processing difficulty in the vitrification facility was a partial failure in the spray calciner nozzle. The Pu byproduct of waste preparation was purified by ion exchange and calcined to oxide; one can of oxide ruptured due to self-heating. 27 figures, 16 tables. (DLC)

• Research Organization: Battelle Pacific Northwest Labs., Richland, WA (USA)
• DOE Contract Number: EY-76-C-06-1830
• OSTI ID: 6086723
• Report Number(s): PNL-3038
• Country of Publication: United States
• Language: English

Related Subjects

052001* -- Nuclear Fuels-- Waste Processing
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
GASEOUS WASTES
HIGH-LEVEL RADIOACTIVE WASTES
MANAGEMENT
NUCLEAR FACILITIES
PERFORMANCE
PHASE TRANSFORMATIONS
PROCESSING
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE FACILITIES
RADIOACTIVE WASTE PROCESSING
RADIOACTIVE WASTES
SOLIDIFICATION
VITRIFICATION
WASTE MANAGEMENT
WASTE PROCESSING
WASTES