FABRICATION AND PROPERTIES OF URANIUM-ZIRCONIUM HYDRIDE FUEL ELEMENTS FOR TRIGA REACTORS

Journal Article · Wed Jan 01 04:00:00 EST 1958 · Am. Inst. Mining Met. Petrol. Engrs., Inst. Metals Div., Spec. Rept. Ser.

OSTI ID:4251663

Wallace, W P; Simnad, M T; Turovlin, B

The melting, casting, extrusion, and machining of 8 wt.% U and 92 wt.% Zr alloy are described; the assembly of the hydrided alloy into a fuel element is described. The fabrication of the uranium -zirconium hydride fuel materials was accomplished with exceptionally high yields, resulting in relatively inexpensive fuel elements. It was found that the use of homogeneous mixture of the fuel and the zirconium hydride moderator in the reactor resulted in a prompt negative temperature coefficient, thus enhancing the safety of the reaetor. The physical, chemical, and mechanical properties of zirconium hydride and uraniumzirconium hydride have been measured. In addition to the prompt negative temperature coefficient, these hydrides have excellent corrosion resistance in water, good thermal shock resistance, and dimensional stability upon thermal cycling and nuclear irradiation. (auth)

• Research Organization: General Atomic Div., General Dynamics Corp., San Diego, Calif.
• NSA Number: NSA-13-013572
• OSTI ID: 4251663
• Journal Information: Am. Inst. Mining Met. Petrol. Engrs., Inst. Metals Div., Spec. Rept. Ser., Journal Name: Am. Inst. Mining Met. Petrol. Engrs., Inst. Metals Div., Spec. Rept. Ser. Vol. Vol: 5, No. 7
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

CASTING
CHEMICALS
CORROSION
EXTRUSION
FABRICATION
FUEL ELEMENTS
IRRADIATION
MACHINING
MEASURED VALUES
MECHANICAL PROPERTIES
MELTING
METALLURGY AND CERAMICS
RADIATION EFFECTS
REACTOR SAFETY
RESEARCH REACTORS
STABILITY
TEMPERATURE
TENSILE PROPERTIES
THERMAL STRESSES
TRIGA SERIES
URANIUM HYDRIDES
WATER
ZIRCONIUM HYDRIDES