Design of a mixing system for simulated high-level nuclear waste melter feed slurries
The Nuclear Waste Treatment Program development program consists of coordinated nonradioactive and radioactive testing combined with numerical modeling of the process to provide a complete basis for design and operation of a vitrification facility. The radioactive demonstration tests of equipment and processes are conducted before incorporation in radioactive pilot-scale melter systems for final demonstration. The mixing system evaluation described in this report was conducted as part of the nonradioactive testing. The format of this report follows the sequence in which the design of a large-scale mixing system is determined. The initial program activity was concerned with gaining an understanding of the theoretical foundation of non-Newtonian mixing systems. Section 3 of this report describes the classical rheological models that are used to describe non-Newtonian mixing systems. Since the results obtained here are only valid for the slurries utilized, Section 4, Preparation of Simulated Hanford and West Valley Slurries, describes how the slurries were prepared. The laboratory-scale viscometric and physical property information is summarized in Section 5, Laboratory Rheological Evaluations. The bench-scale mixing evaluations conducted to define the effects of the independent variables described above on the degree of mixing achieved with each slurry are described in Section 6. Bench-scale results are scaled-up to establish engineering design requirements for the full-scale mixing system in Section 7. 24 refs., 37 figs., 44 tabs.
- Research Organization:
- Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 5957779
- Report Number(s):
- PNL-5745; ON: DE86009039
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
CERAMIC MELTERS
DESIGN
HIGH-LEVEL RADIOACTIVE WASTES
VITRIFICATION
MIXERS
PERFORMANCE TESTING
TURBINES
BENCH-SCALE EXPERIMENTS
CHEMICAL COMPOSITION
DEMONSTRATION PLANTS
DENSITY
EXPERIMENTAL DATA
GLASS
MATHEMATICAL MODELS
PARTICLE SIZE
PH VALUE
QUALITY CONTROL
RADIOACTIVE WASTE PROCESSING
REYNOLDS NUMBER
RHEOLOGY
SHEAR
SLURRIES
VISCOSITY
CONTROL
DATA
DISPERSIONS
ELECTRIC FURNACES
FURNACES
INFORMATION
MACHINERY
MANAGEMENT
MATERIALS
MIXTURES
NUMERICAL DATA
PHYSICAL PROPERTIES
PROCESSING
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
SIZE
SUSPENSIONS
TESTING
TURBOMACHINERY
WASTE MANAGEMENT
WASTE PROCESSING
WASTES
052001* - Nuclear Fuels- Waste Processing