Design and performance of feed delivery systems for simulated radioactive waste slurries
Abstract
Processes for vitrifying simulated high-level radioactive waste have been developed at the Pacific Northwest Laboratory (PNL) over the last several years. Paralleling this effort, several feed systems used to deliver the simulated waste slurry to the melter have been tested. Because there had been little industrial experience in delivering abrasive slurries at feed rates of less than 10 L/min, early experience helped direct the design of more-dependable systems. Also, as feed delivery requirements changed, the feed system was modified to meet these new requirements. The various feed systems discussed in this document are part of this evolutionary process, so they have not been ranked against each other. The four slurry feed systems discussed are: (1) vertical-cantilevered centrifugal pump system; (2) airlift feed systems; (3) pressurized-loop systems; and (4) positive-displacement pump system. 20 figures, 11 tables.
- Authors:
- Publication Date:
- Research Org.:
- Pacific Northwest Lab., Richland, WA (USA)
- OSTI Identifier:
- 6468568
- Report Number(s):
- PNL-4423
ON: DE83008721; TRN: 83-010125
- DOE Contract Number:
- AC06-76RL01830
- Resource Type:
- Technical Report
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; FUEL FEEDING SYSTEMS; DESIGN; PERFORMANCE; RADIOACTIVE WASTE PROCESSING; HIGH-LEVEL RADIOACTIVE WASTES; SOLIDIFICATION; CERAMIC MELTERS; EXPERIMENTAL DATA; SLURRIES; VITRIFICATION; DATA; DISPERSIONS; ELECTRIC FURNACES; FUEL SYSTEMS; FURNACES; INFORMATION; MANAGEMENT; MATERIALS; MIXTURES; NUMERICAL DATA; PHASE TRANSFORMATIONS; PROCESSING; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; SUSPENSIONS; WASTE MANAGEMENT; WASTE PROCESSING; WASTES; 052001* - Nuclear Fuels- Waste Processing
Citation Formats
Perez, J.M. Jr. Design and performance of feed delivery systems for simulated radioactive waste slurries. United States: N. p., 1983.
Web. doi:10.2172/6468568.
Perez, J.M. Jr. Design and performance of feed delivery systems for simulated radioactive waste slurries. United States. doi:10.2172/6468568.
Perez, J.M. Jr. Tue .
"Design and performance of feed delivery systems for simulated radioactive waste slurries". United States.
doi:10.2172/6468568. https://www.osti.gov/servlets/purl/6468568.
@article{osti_6468568,
title = {Design and performance of feed delivery systems for simulated radioactive waste slurries},
author = {Perez, J.M. Jr.},
abstractNote = {Processes for vitrifying simulated high-level radioactive waste have been developed at the Pacific Northwest Laboratory (PNL) over the last several years. Paralleling this effort, several feed systems used to deliver the simulated waste slurry to the melter have been tested. Because there had been little industrial experience in delivering abrasive slurries at feed rates of less than 10 L/min, early experience helped direct the design of more-dependable systems. Also, as feed delivery requirements changed, the feed system was modified to meet these new requirements. The various feed systems discussed in this document are part of this evolutionary process, so they have not been ranked against each other. The four slurry feed systems discussed are: (1) vertical-cantilevered centrifugal pump system; (2) airlift feed systems; (3) pressurized-loop systems; and (4) positive-displacement pump system. 20 figures, 11 tables.},
doi = {10.2172/6468568},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Feb 01 00:00:00 EST 1983},
month = {Tue Feb 01 00:00:00 EST 1983}
}
-
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 ofmore »
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