Statistical experimental design for saltstone mixtures
Conference
·
OSTI ID:5380927
We used a mixture experimental design for determining a window of operability for a process at the 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. {sup 137}Cs 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 salt waste, needed to be determined. The effective diffusion coefficients for NO{sub 3} and Cr were used as a measure of leach rate. Various mixes of cement, Ca(OH){sub 2}, salt, slag and flyash were used. These constituents comprise the whole mix. Thus, a mixture experimental design was used.
- Research Organization:
- Westinghouse Savannah River Co., Aiken, SC (United States)
- Sponsoring Organization:
- DOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC09-89SR18035
- OSTI ID:
- 5380927
- Report Number(s):
- WSRC-MS-91-560; CONF-920606--14; ON: DE92010634
- Country of Publication:
- United States
- Language:
- English
Similar Records
Statistical experimental design for saltstone mixtures
Statistical experimental design for saltstone mixtures
The Product Composition Control System at Savannah River: The statistical process control algorithm. Revision 1
Conference
·
Mon Dec 30 23:00:00 EST 1991
·
OSTI ID:10136735
Statistical experimental design for saltstone mixtures
Conference
·
Tue Dec 31 23:00:00 EST 1991
· Transactions of the American Nuclear Society; (United States)
·
OSTI ID:7066461
The Product Composition Control System at Savannah River: The statistical process control algorithm. Revision 1
Conference
·
Wed Mar 31 23:00:00 EST 1993
·
OSTI ID:10154857
Related Subjects
052001* -- Nuclear Fuels-- Waste Processing
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
BUILDING MATERIALS
CEMENTS
CHROMIUM
CONTAINERS
DIFFUSION
DISPERSIONS
DISSOLUTION
ELEMENTS
GROUTING
LEACHING
MANAGEMENT
MATERIALS
MATHEMATICAL MODELS
MATHEMATICS
METALS
MIXTURES
NATIONAL ORGANIZATIONS
NITRATES
NITROGEN COMPOUNDS
OXYGEN COMPOUNDS
PROCESSING
RADIOACTIVE WASTE MANAGEMENT
RADIOACTIVE WASTE PROCESSING
SALTS
SAVANNAH RIVER PLANT
SEPARATION PROCESSES
SIMULATION
SLUDGES
STATISTICS
TANKS
TRANSITION ELEMENTS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
WASTE MANAGEMENT
WASTE PROCESSING
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
BUILDING MATERIALS
CEMENTS
CHROMIUM
CONTAINERS
DIFFUSION
DISPERSIONS
DISSOLUTION
ELEMENTS
GROUTING
LEACHING
MANAGEMENT
MATERIALS
MATHEMATICAL MODELS
MATHEMATICS
METALS
MIXTURES
NATIONAL ORGANIZATIONS
NITRATES
NITROGEN COMPOUNDS
OXYGEN COMPOUNDS
PROCESSING
RADIOACTIVE WASTE MANAGEMENT
RADIOACTIVE WASTE PROCESSING
SALTS
SAVANNAH RIVER PLANT
SEPARATION PROCESSES
SIMULATION
SLUDGES
STATISTICS
TANKS
TRANSITION ELEMENTS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
WASTE MANAGEMENT
WASTE PROCESSING