THERMAL FLUX IRRADIATION STUDIES OF (U,Pu)C FUEL DESIGN, FABRICATION AND REACTOR INSERTION OF FUEL PINS AND CAPSULES.

Technical Report · Wed Jan 01 00:00:00 EST 1969

DOI:https://doi.org/10.2172/4733475· OSTI ID:4733475

Levine, P. J.

• Research Organization: Westinghouse Electric Corp., Madison, Pa. Advanced Reactors Div.
• DOE Contract Number: AT(30-1)-3791
• NSA Number: NSA-24-001103
• OSTI ID: 4733475
• Report Number(s): WARD-3791-16
• Resource Relation: Other Information: UNCL. Orig. Receipt Date: 31-DEC-70
• Country of Publication: United States
• Language: English

Related Subjects

N30250* -Metals
Ceramics
& Other Materials-Ceramics & Cermets-Radiation Effects
N38700 -Reactor Components
Fuels & Accessories
BONDING
FABRICATION
FUEL ELEMENTS
FUEL PINS
GETR
IRRADIATION
PLUTONIUM CARBIDES
RESEARCH REACTORS
RODS
SAFETY
SODIUM
URANIUM CARBIDES
GENERAL ELECTRIC TEST REACTOR/fuel element testing in
hazards evaluation for
PLUTONIUM CARBIDES/PuC-UC
fabrication into sodium- bonded fuel pins for irradiation testing
REACTOR FUEL ELEMENTS/design and fabrication of sodium-bonded carbide pin-type
URANIUM CARBIDES/PuC-UC
microstructure of clad fuel pins of
URANIUM CARBIDES/PuC-UC
fabrication into sodium-bonded fuel pins for irradiation testing
PLUTONIUM CARBIDES/PuC-UC
microstructure of clad fuel pins of