Mechanical design and fabrication of a prototype facility for processing NaK using a chlorine reaction method
Conference
·
OSTI ID:6529622
A prototype facility has been built at the Idaho National Engineering Laboratory (INEL) to dispose of 180 gal(0.68 m{sup 3}) of radioactively contaminated NaK (sodium-potassium) that have been stored on site for 35 years. The NaK was used as primary coolant for the Experimental Breeder Reactor I (EBR-I) at the INEL and was contaminated during a meltdown of the Mark II core in November 1955. The NaK then was transferred to four containers for temporary storage. The facility process will react the NaK with elemental chlorine using a batch process to produce chemically stable sodium chloride and potassium chloride salts. The first use of the facility will be on a prototype level to verify the method. If results are favorable, the facility will be modified to eventually dispose of the EBR-I NaK. The design and intended operation of the prototype facility are described. 2 figs.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls, ID (USA)
- Sponsoring Organization:
- DOE/NE
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 6529622
- Report Number(s):
- EGG-M-89357; CONF-900210--54; ON: DE91001849
- Country of Publication:
- United States
- Language:
- English
Similar Records
Proposed decommissioning of radioactively contaminated NaK
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Conference
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Thu Oct 01 00:00:00 EDT 1987
·
OSTI ID:5660741
Functional and operational design requirements for decontamination and decommissioning of the EBR-I Mark-II NaK: Final report. [NaK eutectics]
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Tue Sep 01 00:00:00 EDT 1987
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Tue Sep 01 00:00:00 EDT 1987
·
OSTI ID:5654258
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220502* -- Nuclear Reactor Technology-- Environmental Aspects-- Radioactive Effluents
220900 -- Nuclear Reactor Technology-- Reactor Safety
ALKALI METALS
BREEDER REACTORS
CHLORINE
CONTAINERS
COOLANTS
COOLING SYSTEMS
DESIGN
EBR-1 REACTOR
ELEMENTS
ENERGY SYSTEMS
ENERGY TRANSFER
EPITHERMAL REACTORS
EUTECTICS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
HALOGENS
HEAT TRANSFER
HYDRAULICS
INDUSTRIAL PLANTS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MANAGEMENT
MATERIALS
MECHANICS
METALS
NAK COOLED REACTORS
NONMETALS
PLUTONIUM REACTORS
POTASSIUM
POTASSIUM COOLED REACTORS
POWER REACTORS
PROCESSING
RADIOACTIVE EFFLUENTS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE PROCESSING
RADIOACTIVE WASTE STORAGE
RADIOACTIVE WASTES
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SODIUM
STORAGE
TANKS
WASTE MANAGEMENT
WASTE PROCESSING
WASTE PROCESSING PLANTS
WASTE STORAGE
WASTES
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220502* -- Nuclear Reactor Technology-- Environmental Aspects-- Radioactive Effluents
220900 -- Nuclear Reactor Technology-- Reactor Safety
ALKALI METALS
BREEDER REACTORS
CHLORINE
CONTAINERS
COOLANTS
COOLING SYSTEMS
DESIGN
EBR-1 REACTOR
ELEMENTS
ENERGY SYSTEMS
ENERGY TRANSFER
EPITHERMAL REACTORS
EUTECTICS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
HALOGENS
HEAT TRANSFER
HYDRAULICS
INDUSTRIAL PLANTS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MANAGEMENT
MATERIALS
MECHANICS
METALS
NAK COOLED REACTORS
NONMETALS
PLUTONIUM REACTORS
POTASSIUM
POTASSIUM COOLED REACTORS
POWER REACTORS
PROCESSING
RADIOACTIVE EFFLUENTS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE PROCESSING
RADIOACTIVE WASTE STORAGE
RADIOACTIVE WASTES
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SODIUM
STORAGE
TANKS
WASTE MANAGEMENT
WASTE PROCESSING
WASTE PROCESSING PLANTS
WASTE STORAGE
WASTES