MANUFACTURE OF FUEL ELEMENT FOR HIGH TEMPERATURE GAS-COOLED REACTORS

Patent · Tue Oct 31 00:00:00 EST 1961

OSTI ID:4073167

Uranium or uranium oxide and graphite powders are mixed and sintered into uranium carbide inside a can made of a material having a low neutron-capture cross-section such as zirconium and silicon carbides. (EURATOM)

• Research Organization: Originating Research Org. not identified
• NSA Number: NSA-15-021809
• OSTI ID: 4073167
• Report Number(s): BE 581449
• Resource Relation: Patent File Date: 1958 Sep 01; Other Information: Orig. Receipt Date: 31-DEC-61
• Country of Publication: Belgium
• Language: English

Related Subjects

REACTOR TECHNOLOGY
CANNING
CAPTURE
CROSS SECTIONS
FABRICATION
FUEL ELEMENTS
GAS COOLANT
GRAPHITE
HIGH TEMPERATURE
MIXING
NEUTRONS
PATENT
POWDERS
REACTORS
SILICON CARBIDES
SINTERING
URANIUM
URANIUM CARBIDES
URANIUM OXIDES
ZIRCONIUM