The most life-limiting structural component in light-water reactors is the reactor pressure vessel (RPV) because its replacement is not currently considered a viable option. Thus, this research area's goal is to examine and understand the influence of irradiation at high fluences on RPV embrittlement. Additional goals include obtaining data from high fluence surveillance capsules and harvested RPV materials to validate RPV embrittlement prediction models.
Research is directed at removing gaps in the knowledge of RPV performance under long-term aging conditions and incorporating this knowledge into a model that can be used by the industry to make informed aging management decisions, and by the US Nuclear Regulatory Commission to improve guidance.
Development of a new predictive embrittlement trend curve for RPV materials.
Verification of the latest embrittlement trend curve on materials harvested from the decommissioned Zion Unit 1 RPV and the Palisades high fluence surveillance capsule.
Development of mini-CT specimens for fracture toughness characterization of RPV materials.