NSUF 18-CINR-14717: Rapid Simulation of Irradiation Damage in PWR Internals

A significant portion of Pressurized Water Reactor (PWR) core internals, such as baffle-former plates, baffle bolts, core support plates, and core barrels, are fabricated from austenitic stainless steels. All of these are critical components to the successful operation of a PWR. Degradation of austenitic stainless steels are of upmost importance, especially in consideration of a second license renewal. Second license renewal would extend operation to 80 years resulting in PWR core internals reaching significantly higher damage doses (>100 dpa) than those previously anticipated [1]. Industry has expressed urgency to develop techniques capable of determining degradation of core materials in these higher dose regimes based on pre-existing, early in-life microstructures and mechanical performance.

Additional Info

Field	Value
Awarded Institution	University of Michigan
CINR Number	18-14717
Embargo End Date	2028-01-08
NSUF Call	FY 2018 CINR
PI	Kevin Field
Project Member	Dr. Kevin Field, Associate Professor - University of Michigan (https://orcid.org/0000-0002-3105-076X)
Project Notes	Awarded on 08/16/2018
Project Type	CINR
RTE Number	3068