GLASS FIBERS IN NUCLEAR REACTOR TECHNOLOGY
Technical Report
·
OSTI ID:4307205
>A novel technique of incorporating fissionable and fertile material, homogeneously dispersed, in mineral or glass fibers, appears to have definite advantages for use in nuclear reactor fuel elements. To date, incorporation of 10% uranium-235 oxide by weight has been readily achieved. Radiation stability studies were made of these fibers, examining the effect of fiber diameter, tensile strength, and surfuce effects. Fibers of 1 to 5 mu diameter were shown to be excellent sources of fission fragments for utilization in the irradiation synthesis of chemicals, i.e., the nttrogen fixation process. Fibers of over 10 mu in diameter are being considered as matrices of fuel elements for power and materials test nuclear reactors. Some of the advantages of dispersing fissionable, including uranium-233, uranium-235 and plutonium-239, and fertile, including uranium-238 and thorium-232, material in glass fibers are; large surface area per unit, high chemical and thermal stability, adaptability to variations in composition versatility in possible structural forms, and adaptability to simplified chemical reprocessing procedures. (auth)
- Research Organization:
- Rensselaer Polytechnic Inst., Troy, N.Y.; Owens-Corning Fiberglas Corp. Research Center, Newark, Ohio
- NSA Number:
- NSA-12-014999
- OSTI ID:
- 4307205
- Report Number(s):
- A/CONF.15/P/440
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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Related Subjects
ADSORPTION
CANNING
CHEMICAL REACTIONS
CONFERENCE
CONFIGURATION
DISPERSIONS
EFFICIENCY
FERTILE MATERIALS
FIBERS
FISSION PRODUCTS
FISSIONABLE MATERIALS
FUEL CANS
FUEL ELEMENTS
GLASS
HEAT TRANSFER
HOMOGENEOUS REACTORS
IRRADIATION
MATERIALS TESTING
MECHANICAL STRUCTURES
NITROGEN
NUMERICALS
PHYSICS
PLUTONIUM 239
RADIATION CHEMISTRY
RADIATION EFFECTS
REACTOR CORE
REACTORS
REPROCESSING
STABILITY
SURFACES
TENSILE PROPERTIES
THERMAL STRESSES
THORIUM 232
URANIUM 233
URANIUM 235
URANIUM 238
URANIUM OXIDES
CANNING
CHEMICAL REACTIONS
CONFERENCE
CONFIGURATION
DISPERSIONS
EFFICIENCY
FERTILE MATERIALS
FIBERS
FISSION PRODUCTS
FISSIONABLE MATERIALS
FUEL CANS
FUEL ELEMENTS
GLASS
HEAT TRANSFER
HOMOGENEOUS REACTORS
IRRADIATION
MATERIALS TESTING
MECHANICAL STRUCTURES
NITROGEN
NUMERICALS
PHYSICS
PLUTONIUM 239
RADIATION CHEMISTRY
RADIATION EFFECTS
REACTOR CORE
REACTORS
REPROCESSING
STABILITY
SURFACES
TENSILE PROPERTIES
THERMAL STRESSES
THORIUM 232
URANIUM 233
URANIUM 235
URANIUM 238
URANIUM OXIDES