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.


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.


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

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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.


Porosity Swelling and Transmutation Contributions to Conductivity Changes in Some Neutron-irradiated Copper Alloys

Porosity Swelling and Transmutation Contributions to Conductivity Changes in Some Neutron-irradiated Copper Alloys

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Publisher:

Published: 1986

Total Pages:

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Fast-neutron irradiation of alloys for fusion-reactor applications produces bulk changes in density and composition via porosity swelling and transmutation which affect the dc volume electrical and thermal conductivities (sigma=1[rho]sub e/ and K). For the Cu materials of our study, neutron fluences of 2 x 1026n/m2 (E> 0.1 MeV) produced Ni and Zn weight increases of about 0.05 and 0.09%, respectively, and porosity swelling of 0 to 7%; rho/sub e/ accordingly increased as much as 18%. We also determined the individual rho/sub e/ changes due to both swelling and transmutation via use of an appropriate mixing rule and of Matthiessen's law to unmask any residual effects present, e.g., phase or microstructural changes. For four materials - two pure copper and two alumina-dispersion-strengthened (ADS) alloys - subtraction of these deltarho/sub e/'s from the irradiated values yielded or nearly yielded the respective control values. In contrast, the two precipitation-strengthened (PS) alloys studied, MZC and AMZIRC, had relatively large negative residues, apparently indicating effective radiation-induced conductivities.


Brazed Dispersion Strengthened Copper

Brazed Dispersion Strengthened Copper

Author: DJ. Edwards

Publisher:

Published: 1999

Total Pages: 18

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Four types of brazes were used to join sheets of GLIDCOPTM Al25. Miniature tensile specimens were fabricated from the joints and irradiated under various conditions for a study of their response to high temperature neutron irradiation in FFTF Two of the sets of specimens, brazed with TiCuAg and TiCuNi, were found to possess low quality joints because of excessive diffusion of silver into the base metal in the case of the TiCuAg, and melting of the base metal in the case of the TiCuNi. Joints produced with a CuAu braze were satisfactory for the unirradiated state, but transmutation of Au to Hg affected the integrity of the joints irradiated in a below-core position where the transmutation rate per dpa was rather high. A CuAg braze yielded satisfactory joints in the unirradiated state and held up well when the irradiated specimens were tested. However, transmutation of Ag to Cd leads to a high residual radioactivity that may limit the usefulness of this braze after exposure to neutron irradiation.


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 (