The response of dispersion-strengthened copper alloys to high fluence neutron irradiation at 415{degree}C
Conference
·
OSTI ID:10169992
- Missouri Univ., Rolla, MO (United States)
- Pacific Northwest Lab., Richland, WA (United States)
- SCM Metal Products, Bradfordwoods, PA (United States)
Various oxide-dispersion-strengthened copper alloys have been irradiated to 150 dpa at 415{degree}C in the Fast Flux Test Facility (FFTF). The Al{sub 2}0{sub 3} - strengthened GlidCop{trademark} alloys, followed closely by a HfO{sub 2} - strengthened alloy, displayed the best swelling resistance, electrical conductivity, and tensile properties. The conductivity of the HfO{sub 2} - 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 Cr{sub 2}0{sub 3} - strengthened alloy showed poor resistance to radiation.
- Research Organization:
- Pacific Northwest Lab., Richland, WA (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 10169992
- Report Number(s):
- PNL-SA--19956; CONF-920673--9; ON: DE92019434
- Country of Publication:
- United States
- Language:
- English
Similar Records
The response of dispersion-strengthened copper alloys to high fluence neutron irradiation at 415 degree C
Irradiation performance of oxide dispersion strengthened copper alloys to 150 dpa at 415 degree C
Irradiation performance of oxide dispersion strengthened copper alloys to 150 dpa at 415{degree}C
Conference
·
Mon Jun 01 00:00:00 EDT 1992
·
OSTI ID:7033957
Irradiation performance of oxide dispersion strengthened copper alloys to 150 dpa at 415 degree C
Conference
·
Thu Oct 31 23:00:00 EST 1991
·
OSTI ID:5926629
Irradiation performance of oxide dispersion strengthened copper alloys to 150 dpa at 415{degree}C
Conference
·
Thu Oct 31 23:00:00 EST 1991
·
OSTI ID:10109336
Related Subjects
36 MATERIALS SCIENCE
360103
360106
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700480
COMPONENT DEVELOPMENT
COPPER BASE ALLOYS
DAMAGING NEUTRON FLUENCE
DIVERTORS
ITER TOKAMAK
MATERIALS STUDIES
MECHANICAL PROPERTIES
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
SWELLING
THERMONUCLEAR REACTOR MATERIALS
ULTIMATE STRENGTH
YIELD STRENGTH
360103
360106
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700480
COMPONENT DEVELOPMENT
COPPER BASE ALLOYS
DAMAGING NEUTRON FLUENCE
DIVERTORS
ITER TOKAMAK
MATERIALS STUDIES
MECHANICAL PROPERTIES
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
SWELLING
THERMONUCLEAR REACTOR MATERIALS
ULTIMATE STRENGTH
YIELD STRENGTH