Advancements in Materials for Next Generation Nuclear Reactor

Our research focuses on the development and evaluation of advanced nuclear fuel cladding materials. We are investigating the radiation resistance of advanced ferritic/martensitic stainless steels and establishing microstructure–property correlations in reactor materials using in-situ high-energy X-ray techniques. Additional efforts include the development of nano-structured bulk austenitic stainless steels with enhanced radiation tolerance, the creation of novel vanadium-based diffusion coatings to mitigate fuel–cladding chemical interactions, and the improvement of accident tolerance in existing zirconium-based cladding systems. We are also assessing the performance and reliability of additively manufactured 304 and 316L stainless steel components for nuclear applications.

Supporting Regulation and License Renewal for Existing Nuclear Reactors

Our work supports the continued safe operation of the current reactor fleet by evaluating the effects of thermal aging and low-dose neutron irradiation on core structural materials, such as cast stainless steels and weldments. The outcomes of these studies are designed to provide technical evidence to inform the U.S. Nuclear Regulatory Commission (NRC) in decisions related to license renewal and long-term reactor operation.

Nuclear Fuels

We conduct comprehensive studies of nuclear fuel performance under operational and extreme conditions, with a particular focus on structural evolution and changes in thermophysical properties. Our findings have played a critical role in benchmarking simulation tools developed under the Department of Energy’s Nuclear Energy Advanced Modeling and Simulation (NEAMS) program. In addition, our work characterizing irradiated UCO TRISO fuel kernels supports the certification, licensing, and commercialization of TRISO fuel. In recent years, our team has contributed significantly to a DOE Level 3 milestone report that advanced national efforts in fuel qualification.