The Role of Grain Size on Neutron Irradiation Response of Nanocrystalline Copper
- North Carolina State Univ., Raleigh, NC (United States); DOE/OSTI
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- North Carolina State Univ., Raleigh, NC (United States)
The role of grain size on the developed microstructure and mechanical properties of neutron irradiated nanocrystalline copper was investigated by comparing the radiation response of material to the conventional micrograined counterpart. Nanocrystalline (nc) and micrograined (MG) copper samples were subjected to a range of neutron exposure levels from 0.0034 to 2 dpa. At all damage levels, the response of MG-copper was governed by radiation hardening manifested by an increase in strength with accompanying ductility loss. Conversely, the response of nc-copper to neutron irradiation exhibited a dependence on the damage level. At low damage levels, grain growth was the primary response, with radiation hardening and embrittlement becoming the dominant responses with increasing damage levels. Annealing experiments revealed that grain growth in nc-copper is composed of both thermally-activated and irradiation-induced components. Tensile tests revealed minimal change in the source hardening component of the yield stress in MG-copper, while the source hardening component was found to decrease with increasing radiation exposure in nc-copper.
- Research Organization:
- Idaho National Laboratory (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy (NE)
- Grant/Contract Number:
- AC07-05ID14517
- OSTI ID:
- 1628450
- Journal Information:
- Materials, Journal Name: Materials Journal Issue: 3 Vol. 9; ISSN MATEG9; ISSN 1996-1944
- Publisher:
- MDPICopyright Statement
- Country of Publication:
- United States
- Language:
- English
Similar Records
Radiation tolerant nanocrystalline ZrN films under high dose heavy-ion irradiations
Tensile and electrical properties of copper alloys irradiated in a fission reactor
Journal Article
·
Tue Apr 14 00:00:00 EDT 2015
· Journal of Applied Physics
·
OSTI ID:22402855
Tensile and electrical properties of copper alloys irradiated in a fission reactor
Technical Report
·
Sun Mar 31 23:00:00 EST 1996
·
OSTI ID:272145