Published July 1993 | Version v1
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The response of dispersion-strengthened copper alloys to high fluence neutron irradiation at 415 degrees C

  • 1. Univ. of Missouri, Rolla, MO (United States)
  • 2. Pacific Northwest Laboratory, Richland, WA (United States)

Description

Various oxide-dispersion-strengthened copper alloys have been irradiated to 150 dpa at 415 degrees 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 results in significantly higher swelling for a series of castable oxide-dispersion-strengthened alloys, while a Cr2O3-strengthened alloy showed poor resistance to radiation

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Part of:
Fusion reactor materials semiannual progress report for the period ending March 31, 1993

Additional details

Publishing Information

Imprint Title
Fusion reactor materials semiannual progress report for the period ending March 31, 1993
Imprint Pagination
524 p.
Journal Page Range
p. 331-344.
Report number
DOE/ER--0313/14

Optional Information

Contract/Grant/Project number
Contract AC06-76RL01830