Microstructural evolution in fast-neutron-irradiated austenitic stainless steels
The purpose of this work was to provide additional understanding about mechanisms that determine microstructural evolution in current fast-reactor environments and to identify the sensitivity of this evolution to changes in the He/dpa ratio. This latter sensitivity is of interest because the He/dpa ratio in a fusion reactor first wall will be about 30 times that in fast-reactor fuel cladding. The approach followed in the present work was to used a combination of theoretical and experimental analysis. The experimental component of the work primarily involved the examination by transmission electron microscopy of specimens of a model austenitic alloy that had been irradiated in the Oak Ridge Research Reactor. Some of these specimens had been implanted with helium and subsequently annealed at various temperatures prior to irradiation. The as-implanted-and-aged microstructures were also characterized. A major aspect of the theoretical work was the development of a comprehensive model of microstructural evolution. This included explicit models for the evolution of the major extended defects observed in neutron-irradiated steels: cavities, Frank faulted loops and the dislocation network. Results indicate that the various extended defects evolve in a highly coupled manner.
- Research Organization:
- California Univ., Santa Barbara (USA)
- OSTI ID:
- 6704097
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
360102 -- Metals & Alloys-- Structure & Phase Studies
360106* -- Metals & Alloys-- Radiation Effects
ALLOYS
AUSTENITIC STEELS
BEAMS
CHARGED PARTICLES
CHROMIUM ALLOYS
CORROSION RESISTANT ALLOYS
CRYSTAL STRUCTURE
ELECTRON MICROSCOPY
HELIUM IONS
ION IMPLANTATION
IONS
IRON ALLOYS
IRON BASE ALLOYS
MICROSCOPY
MICROSTRUCTURE
NEUTRON BEAMS
NUCLEON BEAMS
PARTICLE BEAMS
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
STAINLESS STEELS
STEELS
TRANSMISSION ELECTRON MICROSCOPY