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
Abstract	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.
Award Announced Date	2020-01-08T00:00:00
Awarded Institution	None
Facility	None
Facility Tech Lead
Irradiation Facility	None
PI	Kevin Field
PI Email	[email protected]
Project Type	CINR
RTE Number	3068