Pressurized water nuclear reactors in the United States generate about 13 percent of U.S. electricity. Though efficient, these reactors face a unique challenge with stress corrosion cracking (SCC). This type of corrosion is one of the primary life-limiting degradation mechanisms of nickel-base alloy pressure boundary components, such as instrumentation and control rod nozzles, the welds that attach these nozzles to the reactor vessel, and welds that connect feedwater piping to the reactor vessel. As interest grows in a more sustainable and efficient fleet of nuclear reactors across the world, there is increasing interest in characterizing SCC initiation response.

At the Department of Energy's Pacific Northwest National Laboratory, we are developing sophisticated mathematical techniques and software tools to securely manage and analyze vast amounts of data.