Development of processes and equipment for the refabrication of HTGR fuels
Refabrication is in the step in the HTGR thorium fuel cycle that begins with a nitrate solution containing /sup 238/U and culminates in the assembly of this material into fuel elements for use in an HTGR. Refabrication of HTGR fuel is essentially a manufacturing operation and consists of preparation of fuel kernels, application of multiple layers of pyrolytic carbon and SiC, preparation of fuel rods, and assembly of fuel rods in fuel elements. All the equipment for refabrication of /sup 238/U-containing fuel must be designed for completely remote operation and maintenance in hot cell facilities. This paper describes the status of processes and equipment development for the remote refabrication of HTGR fuels. The feasibility of HTGR refabrication processes has been proven by laboratory development. Engineering-scale development is now being performed on a unit basis on the majority of the major equipment items. Engineering-scale equipment described includes full-scale resin loading equipment, a 5-in.-dia (0.13-m) microsphere coating furnace, a fuel rod forming machine, and a cure-in-place furnace.
- Research Organization:
- Oak Ridge National Lab., Tenn. (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 7362006
- Report Number(s):
- ORNL/TM-5334
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
050400 -- Nuclear Fuels-- Feed Processing
050700* -- Nuclear Fuels-- Fuels Production & Properties
050800 -- Nuclear Fuels-- Spent Fuels Reprocessing
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210300 -- Power Reactors
Nonbreeding
Graphite Moderated
ACTINIDE COMPOUNDS
ACTINIDE ISOTOPES
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ALPHA DECAY RADIOISOTOPES
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CARBON COMPOUNDS
CHALCOGENIDES
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GRAPHITE MODERATED REACTORS
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NUCLEI
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OXYGEN COMPOUNDS
PYROLYTIC CARBON
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050700* -- Nuclear Fuels-- Fuels Production & Properties
050800 -- Nuclear Fuels-- Spent Fuels Reprocessing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210300 -- Power Reactors
Nonbreeding
Graphite Moderated
ACTINIDE COMPOUNDS
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
CARBIDES
CARBON
CARBON COMPOUNDS
CHALCOGENIDES
COATED FUEL PARTICLES
CONTROL
ELEMENTS
EQUIPMENT
EVEN-ODD NUCLEI
FABRICATION
FUEL CYCLE
FUEL ELEMENTS
FUEL PARTICLES
FUEL RODS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HEAVY NUCLEI
HTGR TYPE REACTORS
ISOTOPES
NONMETALS
NUCLEI
OXIDES
OXYGEN COMPOUNDS
PYROLYTIC CARBON
RADIOISOTOPES
REACTOR COMPONENTS
REACTORS
REMOTE CONTROL
SILICON CARBIDES
SILICON COMPOUNDS
URANIUM 233
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM ISOTOPES
URANIUM OXIDES
YEARS LIVING RADIOISOTOPES