Published August 1995 | Version v1
Journal article

Temperature and dose dependencies of microstructure and hardness of neutron irradiated OFHC copper

  • 1. Risoe National Lab., Roskilde (Denmark). Materials Dept.

Description

Tensile specimens of pure oxygen free high conductivity (OFHC) copper were irradiated with fission neutrons between 320 and 723 K to fluences in the range 5x1021 to 1.5x1024 n/m2 (E>1 MeV) with a flux of 2.5x1017 n/m2 s. Irradiated specimens were investigated by transmission electron microscopy (TEM) and quantitative determinations were made of defect clusters and cavities. The dose dependence of tensile properties of specimens irradiated at 320 K was determined at 295 K. Hardness measurements were made at 295 K on specimens irradiated at different temperatures and doses. Microstructures of tensile tested specimens were also investigated by TEM. Results show that the increase in cluster density and hardening nearly saturate at a dose of similar 0.3 dpa. Irradiations at 320 K cause a drastic decrease in the uniform elongation already at ∼ =0.1 dpa. It is suggested that the irradiation-induced increase in the initial yield stress and a drastic decrease in the ability of copper to deform plastically in a homogeneous fashion are caused by a substantial reduction in the ability of grown-in dislocations to act as efficient dislocation sources. ((orig.))

Additional details

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
224
Journal Issue
2
Journal Page Range
p. 131-140.
ISSN
0022-3115
CODEN
JNUMAM