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.

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:

Publisher:

Published: 1992

Total Pages: 41

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 Al203 - strengthened GlidCop{trademark} 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 Cr203 - strengthened alloy showed poor resistance to radiation.

The Response of Dispersion-strengthened Copper Alloys to High Fluence Neutron Irradiation at 415 Degree C.
The Response of Dispersion-strengthened Copper Alloys to High Fluence Neutron Irradiation at 415 Degree C.

Author:

Publisher:

Published: 1992

Total Pages: 41

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 Al203 - strengthened GlidCop{trademark} 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 Cr203 - strengthened alloy showed poor resistance to radiation.

Response of Solute and Precipitation-strengthened Copper Alloys at High Neutron Exposure
Response of Solute and Precipitation-strengthened Copper Alloys at High Neutron Exposure

Author:

Publisher:

Published: 1991

Total Pages: 23

ISBN-13:

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A variety of solute and precipitation strengthened copper base alloys have been irradiated to neutron-induced displacement levels of 34 to 150 dpa at 415°C and 32 dpa at 529°C in the Fast Flux Test Facility to assess their potential for high heat flux applications in fusion reactors. Several MZC-type alloys appear to offer the most promise for further study. For low fluence applications CuBeNi and spinodally strengthened CuNiTi alloys may also be suitable. Although Cu-2Be resists swelling, it is not recommended for fusion reactor applications because of its low conductivity.

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.