NSUF 14-474: Radiation Induced Segregation (RIS) in Ni-Cr Alloys

Austenitic stainless steels and Ni-based alloys are widely used structural materials in light water nuclear reactors (LWR). Although the degradation mechanisms in these classes of alloys under irradiation have been extensively studied, the point defect kinetics are not fully understood. Thermo-kinetics of point defects contributes to creep, grain growth, corrosion, and the radiation response in these materials. All these effects are of immediate practical importance for nuclear power plant lifetime management. The proposed research will aim to clarify point defect thermo-kinetics under irradiation by using binary Ni-5%Cr and Ni-18%Cr alloys. The research is well-aligned with the DOE-NE’s of LWR Sustainability Program. The proposed ATR-NSUF experimental work will involve transmission electron microscopy in conjunction with energy-dispersive x-ray spectroscopy (TEM-EDS), and sample preparation by focused ion beam (FIB). Prior preparing the TEM samples, the grain boundaries will be selected based on SEM/EBSD (carried out at UW). A systematic study on the effects of grain boundary type, grain size, and composition on RIS will be carried out. The results are expected to give new insight on fundamental point defect interactions under irradiation. The work at CAES is proposed to be carried out early 2014.

Tilleggsinformasjon

Felt	Verdi
Awarded Institution	University of Wisconsin
Embargo End Date	2026-02-27
Facility Tech Lead	Mukesh Bachhav
NSUF Call	FY 2014 RTE 1st Call
PI	Janne Pakarinen
Project Member	Dr. Mitra Taheri, Professor - Johns Hopkins University
Project Member	Janne Pakarinen - Consultant
Project Member	Professor Kumar Sridharan, Professor - University of Wisconsin
Project Type	RTE
RTE Number	474