Mechanical Property Changes and Microstructures of Dispersion-Strengthened Copper Alloys After Neutron Irradiation at 411, 414, and 529°C
Mechanical Property Changes and Microstructures of Dispersion-Strengthened Copper Alloys After Neutron Irradiation at 411, 414, and 529°C

Author: KR. Anderson

Publisher:

Published: 1992

Total Pages: 21

ISBN-13:

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Dispersion-strengthened copper alloys have shown promise for certain high heat flux applications in both near-term and long-term fusion devices. This study examines mechanical properties changes and microstructural evolution in several oxide dispersion-strengthened alloys which were subjected to high levels of irradiation-induced displacement damage. Irradiations were carried out in the fast flux test facility (FFTF) to 34 and 50 dpa at 411 to 414°C and 32dpa at 529°C.

Dispersion Strengthened Copper-thorium Boride and Copper-alumina Alloys Produced by Melting and Casting
Dispersion Strengthened Copper-thorium Boride and Copper-alumina Alloys Produced by Melting and Casting

Author: Gilbert J. London

Publisher:

Published: 1959

Total Pages: 100

ISBN-13:

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This report describes work on producing dispersion strengthened copper alloys using melting and casting techniques as opposed to more conventionally used powder metallurgy techniques. Two methods of approach are described. One method produces copper-thorium boride alloys by liquid phase precipitation. Cu-2% ThB4 alloys produced by this technique show 10 to 80% improved tensile properties, two-to-three orders of magnitude improved creep and stress-rupture properties together with a 2 to 10% increase in electrical resistivity. The second method produces a copper-aluminum oxide alloy by a solid state diffusion reaction following melting and casting. The precipitate formed is extremely fine, resisting recrystallization at 1000C for 24 hours. (Author).

The Response of Dispersion-Strengthened Copper Alloys to High Fluence Neutron Irradiation at 415°C
The Response of Dispersion-Strengthened Copper Alloys to High Fluence Neutron Irradiation at 415°C

Author: DJ. Edwards

Publisher:

Published: 1994

Total Pages: 20

ISBN-13:

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Various oxide-dispersion-strengthened copper alloys have been irradiated to 150 dpa at 415°C in the Fast Flux Test Facility (FFTF). The Al2O3-strengthened GlidCopTM alloys, followed closely by a HfO2-strengthened alloy, displayed the best swelling resistance, electrical conductivity, and tensile properties. The conductivity of the HfO2-strengthened alloy reached a plateau at the higher levels of irradiation, instead of exhibiting the steady decrease in conductivity observed in the other alloys. A high initial oxygen content resulted in significantly higher swelling for a series of castable oxide-dispersion-strengthened alloys, while a Cr2O3-strengthened alloy showed poor resistance to radiation.