CX-270184: Development and Integration of Light Water Reactor (LWR) Materials Corrosion Degradation Codes into Grizzly – University of California at Berkeley

The University of California, Berkeley proposes to develop deterministic, physico chemical models for predicting the accumulation of localized corrosion damage in the primary coolant circuits of the currently operating fleet of light water reactors. The successful modeling of the accumulation in the primary coolant circuits will require the experimental measurement of kinetic parameters for hydrogen evolution, the reduction of oxygen, and the electro-dissolution of the alloys.