NSUF 23-1908: Microstructural characterization of neutron irradiated C-C composites

In recent years the nuclear industry has considered C-C composites a potential material for Gen IV reactors. However, there is very limited information on neutron-induced damage in the phases of C-C composites. To investigate the phases of C-C composites, it is necessary to employ advanced characterization, such as Scanning Electron Microscopy (SEM) and some techniques related to Transmission Electron Microscopy (TEM). In this research, SEM will be used to investigate any bulk damage generated from neutron-induced dimensional change. In contrast, Scanning Transmission Electron Microscopy (STEM) combined with Electron Energy Loss Spectroscopy (EELS) will be used to study the effects of irradiation on the different phases of the C-C composites. TEM data in C-C composites is currently unavailable, limiting the understanding of defects subjected to irradiation conditions that may be found in Generation IV reactors designs. The study of C-C composites irradiated at the proposed irradiation conditions would improve the fundamental understanding of the defect mobility and evolution in these materials.

Additional Info

Field	Value
Abstract	In recent years the nuclear industry has considered C-C composites a potential material for Gen IV reactors. However, there is very limited information on neutron-induced damage in the phases of C-C composites. To investigate the phases of C-C composites, it is necessary to employ advanced characterization, such as Scanning Electron Microscopy (SEM) and some techniques related to Transmission Electron Microscopy (TEM). In this research, SEM will be used to investigate any bulk damage generated from neutron-induced dimensional change. In contrast, Scanning Transmission Electron Microscopy (STEM) combined with Electron Energy Loss Spectroscopy (EELS) will be used to study the effects of irradiation on the different phases of the C-C composites. TEM data in C-C composites is currently unavailable, limiting the understanding of defects subjected to irradiation conditions that may be found in Generation IV reactors designs. The study of C-C composites irradiated at the proposed irradiation conditions would improve the fundamental understanding of the defect mobility and evolution in these materials.
Award Announced Date	2023-02-08T10:50:25.573
Awarded Institution	None
Facility	None
Facility Tech Lead	Kory Linton
Irradiation Facility	None
PI	Lee Margetts
PI Email	[email protected]
Project Type	RTE
RTE Number	4600