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.

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Published: 1992

Total Pages: 41

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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°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

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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.

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

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Published: 1991

Total Pages: 23

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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.

The Effect of Neutron Spectrum on the Mechanical and Physical Properties of Pure Copper and Copper Alloys
The Effect of Neutron Spectrum on the Mechanical and Physical Properties of Pure Copper and Copper Alloys

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Published: 2001

Total Pages:

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The electrical resistivity and tensile properties of copper and oxide dispersion strengthened (DS) copper alloys have been measured before and after fission neutron irradiation to damage levels of 0.5 to 5 displacements per atom (dps) at[approximately]100 to 400[degrees]C. Some of the specimens were irradiated inside a 1.5 mm Cd shroud in order to reduce the thermal neutron flux. The electrical resistivity data could be separated into two components, a solid transmutation component[Delta][rho][sub tr] which was proportional to thermal neutron fluence and a radiation defect component[Delta][rho][sub rd] which was independent of the displacement dose. The saturation value for[Delta][rho][sub rd] was[approximately]1.2 nanohm-meters for pure copper and[approximately]1.6 nanohm-meters for the DS copper alloys irradiated at 100[degrees]C in positions with a fast-to-thermal neutron flux ratio of 5. Considerable radiation hardening was observed in all specimens at irradiation temperatures below 200[degrees]C. The yield strength was relatively insensitive to neutron spectrum in specimens strengthened by dispersoids or cold- working. 17 refs., 7 figs., 1 tab.

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

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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.

Neutron Irradiation Induced High Temperature Embrittlement of Pure Copper and High Strength Copper Alloys
Neutron Irradiation Induced High Temperature Embrittlement of Pure Copper and High Strength Copper Alloys

Author: SJ. Zinkle

Publisher:

Published: 2000

Total Pages: 17

ISBN-13:

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The effect of helium production during neutron irradiation on the high temperature tensile properties of copper and dispersion strengthened (DS) copper alloys was investigated in neutron-irradiated specimens containing different levels of boron. Sheet tensile specimens were irradiated at temperatures of 90°C, 150°C and 300°C to doses of 0.2-1 dpa. Considerable embrittlement (