NSUF 19-1695: TEM Characterization of Highly Irradiated Stainless Steel

The microstructural evolution of key reactor components, and the associated change in properties, are key to safe reactor operations and continued lifetime extension plans. One class of materials that are used for in-core components are the 300-class of stainless steels. In this work, we seek to perform a detailed microstructural analysis on samples of a 304 stainless steel that has been irradiated to doses of 69, 96, and 125 dpa. The work to be conducted under this proposal will focus on using TEM methods to characterize the microstructure of the materials when irradiated to these high doses. Specific attention will be paid to a detailed characterization of the dislocation loop population, including size distributions, number density, and Burgers vector. Chemical changes to the material will also be investigated through STEM-EDS analysis. The work should be complete within 6 months of initiation. The scientific output will be a better/deeper understanding of microstructural response of stainless steels to high dose irradiation.

Informazioni addizionali

Campo	Valore
Awarded Institution	Oak Ridge National Laboratory
Embargo End Date	2021-03-04
Facility Tech Lead	Kory Linton
NSUF Call	FY 2019 RTE 1st Call
PI	Philip Edmondson
Project Member	Dr. Philip Edmondson - University of Manchester (https://orcid.org/0000-0001-8990-0870)
Project Member	Karl Whittle - University of Liverpool (https://orcid.org/0000-0002-8000-0857)
Project Notes	Awarded on 02/08/2019
Project Type	RTE
RTE Number	1695