Statistical experimental design for saltstone mixtures

Conference · Wed Jan 01 04:00:00 EST 1992 · Transactions of the American Nuclear Society; (United States)

OSTI ID:7066461

Harris, S P; Postles, R L ^[1]

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1. Westinghouse Savannah River Co., Aiken, SC (United States)

The authors used a mixture experimental design for determining a window of operability for a process at the U.S. Department of Energy, Savannah River Site, Defense Waste Processing Facility (DWPF). The high-level radioactive waste at the Savannah River Site is stored in large underground carbon steel tanks. The waste consists of a supernate layer and a sludge layer. Cesium-137 will be removed from the supernate by precipitation and filtration. After further processing, the supernate layer will be fixed as a grout for disposal in concrete vaults. The remaining precipitate will be processed at the DWPF with treated waste tank sludge and glass-making chemicals into borosilicate glass. The leach-rate properties of the supernate grout formed from various mixes of solidified coefficients for NO{sub 3} and chromium were used as a measure of leach rate. Various mixes of cement, Ca(OH){sub 2}, salt, slag, and fly ash were used. These constituents comprise the whole mix. Thus, a mixture experimental design was used. The regression procedure (PROC REG) in SAS was used to produce analysis of variance (ANOVA) statistics. In addition, detailed model diagnostics are readily available for identifying suspicious observations. For convenience, trillinear contour (TLC) plots, a standard graphics tool for examining mixture response surfaces, of the fitted model were produced using ECHIP.

• OSTI ID: 7066461
• Report Number(s): CONF-920606--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 65
• 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
ALKALI METAL ISOTOPES
ALLOYS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BUILDING MATERIALS
CARBON STEELS
CEMENTS
CESIUM 137
CESIUM ISOTOPES
CONTAINERS
DISSOLUTION
FILTRATION
GROUTING
HIGH-LEVEL RADIOACTIVE WASTES
INTERMEDIATE MASS NUCLEI
IRON ALLOYS
IRON BASE ALLOYS
ISOTOPES
LEACHING
LOW-LEVEL RADIOACTIVE WASTES
MANAGEMENT
MATERIALS
MATHEMATICAL MODELS
NATIONAL ORGANIZATIONS
NUCLEAR FACILITIES
NUCLEI
ODD-EVEN NUCLEI
PRECIPITATION
PROCESSING
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE FACILITIES
RADIOACTIVE WASTE MANAGEMENT
RADIOACTIVE WASTE PROCESSING
RADIOACTIVE WASTES
RADIOISOTOPES
SAVANNAH RIVER PLANT
SEPARATION PROCESSES
SLUDGES
STEELS
TANKS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
VITRIFICATION
WASTE MANAGEMENT
WASTE PROCESSING
WASTE RETRIEVAL
WASTES
YEARS LIVING RADIOISOTOPES