Characterization of double-shell slurry feed grout produced in a pilot-scale test

Technical Report · Tue Dec 01 04:00:00 EST 1992

DOI:https://doi.org/10.2172/6601976· OSTI ID:6601976

Lokken, R O; Martin, P F.C.; Shade, J W

Current plans for disposal of the low-level fraction of selected double-shell tank (DST) wastes at Hanford, Washington include grouting. Grout disposal in this context is the process of mixing low-level liquid waste with cementitious powders. and pumping the resultant slurry to near-surface, underground concrete vaults. Once the slurry is in the vaults. the hydration reactions that occur result in the formation of a highly impermeable solid product that binds and encapsulates the radioactive and hazardous constituents. Westinghouse Hanford Company (WHC) operates the Grout Treatment Facility (GTF) for the US Department of Energy (DOE). Pacific Northwest Laboratory(a) (PNL) provides support to the Grout Disposal Program through laboratory support activities, radioactive grout leach testing. performance assessments, and pilot-scale tests. A pilot-scale test was conducted in November 1988 using a simulated Double-Shell Slurry Feed (DSSF) waste. The main objective of the pilot-scale test was to demonstrate the processability of a DSSF grout formulation that was developed using laboratory equipment and to provide information on scale-up. The dry blend used in this test included 47 wt% class F fly ash, 47 wt% blast furnace slag, and 6 wt% type I/II portland cement. The dry blend was mixed with the simulated waste at a ratio of 9 lb/gal and pumped to a 2800-gal, insulated tank at about 10.4 gpm. Samples of simulated DSSF waste. dry blend, grout slurry, and cured grout were obtained during and after the pilot-scale test for testing and product characterization. Major conclusions of these activities are included.

• Research Organization: Pacific Northwest Lab., Richland, WA (United States)
• Sponsoring Organization: DOE; USDOE, Washington, DC (United States)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 6601976
• Report Number(s): PNL-7979; ON: DE93007179
• Country of Publication: United States
• Language: English

Related Subjects

052001* -- Nuclear Fuels-- Waste Processing
052002 -- Nuclear Fuels-- Waste Disposal & Storage
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
COHERENT SCATTERING
COMPRESSIBILITY
CRYSTAL STRUCTURE
DIFFRACTION
DISSOLUTION
EQUIPMENT
FLUID FLOW
GROUND DISPOSAL
GROUTING
HANFORD RESERVATION
HYDRATION
INDUSTRIAL PLANTS
LEACHING
LOW-LEVEL RADIOACTIVE WASTES
MANAGEMENT
MATERIALS
MATERIALS HANDLING EQUIPMENT
MATHEMATICAL MODELS
MECHANICAL PROPERTIES
MICROSTRUCTURE
MIXERS
NATIONAL ORGANIZATIONS
NUCLEAR FACILITIES
PH VALUE
PHYSICAL PROPERTIES
PROCESSING
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE FACILITIES
RADIOACTIVE WASTE MANAGEMENT
RADIOACTIVE WASTE PROCESSING
RADIOACTIVE WASTES
RHEOLOGY
SCATTERING
SEPARATION PROCESSES
SIMULATION
SOLVATION
SPECTROSCOPY
THERMAL CONDUCTIVITY
THERMODYNAMIC PROPERTIES
THERMODYNAMICS
TOXICITY
US DOE
US ERDA
US ORGANIZATIONS
WASTE DISPOSAL
WASTE MANAGEMENT
WASTE PROCESSING
WASTE PROCESSING PLANTS
WASTES
X-RAY DIFFRACTION