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Tensile and electrical properties of copper alloys irradiated in a fission reactor

Technical Report ·
DOI:https://doi.org/10.2172/272145· OSTI ID:272145
 [1];  [2]; ;  [3]
  1. D.V. Efremov Inst., St. Petersburg (Russian Federation)
  2. Scientific Research Inst. of Atomic Reactors, Dimitrovgrad (Russian Federation)
  3. Oak Ridge National Laboratory, TN (United States); and others
Postirradiation electrical sensitivity and tensile measurements have been completed on pure copper and copper alloy sheet tensile specimens irradiated in the SM-2 reactor to doses of {approx}0.5 to 5 dpa and temperatures between {approx}80 and 400{degrees}C. Considerable radiation hardening and accompanying embrittlement was observed in all of the specimens at irradiation temperature below 200{degrees}C. The radiation-induced electrical conductivity degradation consisted of two main components: solid transmutation effects and radiation damage (defect cluster and particle dissolution) effects. The radiation damage component was nearly constant for the doses in this study, with a value of {approx}1.2n{Omega}m for pure copper and {approx}1.6n{Omega}m for dispersion strengthened copper irradiated at {approx}100{degrees}C. The solid transmutation component was proportional to the thermal neutron flux, and became larger than the radiation damage component for fluences larger than {approx}5 10{sup 24} n.m{sup 2}. The radiation hardening and electrical conductivity degradation decreased with increasing irradiation temperature, and became negligible for temperatures above {approx}300{degrees}C.
Research Organization:
Oak Ridge National Lab., TN (United States)
DOE Contract Number:
AC05-96OR22464
OSTI ID:
272145
Report Number(s):
DOE/ER--0313/19; ORNL/M--5023; ON: DE96010874
Country of Publication:
United States
Language:
English