Lattice Structured Lightweight Structural Materials
The development of lightweight structural materials is crucial for enhancing the performance and deployment feasibility of fission batteries. This study aims to produce lightweight structural materials whose strength-to-weight ratios exceed those of current widely used structural materials. To achieve this, advanced modeling and simulation tools were employed to design lattice structures with different lattice parameters […]
Impact of Irradiation on Microstructure and Mechanical Properties of Materials Produced by Advanced Manufacturing
Advanced non-light water reactor designs, known as Generation IV (Gen IV) reactors, typically operate at higher temperatures and under more extreme radiation conditions than conventional light water reactors. A critical aspect of the successful deployment and advancement of Gen IV reactor designs is the selection of appropriate structural materials for specific applications, which necessitates the […]
Advancing High-Entropy Alloys Research in Nuclear Energy through User Facilities
High-entropy alloys (HEAs), known for their unique compositional complexity and exceptional mechanical properties, have garnered significant interest for applications in extreme environments, such as energy, aerospace and nuclear industries. However, a significant challenge in deploying HEAs in the nuclear energy sector is the current lack of data on the irradiation performance of HEAs. Nuclear Science […]
Promoting regulatory acceptance of combined ion and neutron irradiation testing of nuclear reactor materials: Modeling and software considerations
As the needs for the nuclear energy industry continue to evolve in the 21st century century, timely adoption of new technological solutions acceptable to regulatory agencies is critical. Quantitative prediction of radiation damage in materials and its impact on mechanical properties is a key component of licensing and regulatory decisions regarding nuclear power plants. Accelerated […]
Diffusion behavior of oversized fission products in bcc Fe cladding: A First-Principles Study
Fuel-Cladding Chemical Interaction (FCCI) poses significant challenges in nuclear reactors, where fission products from nuclear fuel interact with Fe-based cladding materials, potentially compromising their structural integrity. This study investigates the diffusion behavior of oversized fission products, Pr, Nd, Ce, and La, within bcc Fe cladding using density functional theory (DFT), nudged elastic band (NEB) method, […]
Nuclear Materials Harvesting and Beyond: Materials Acquisition, Sample Library, and Concrete-Related Research through NSUF
The presentation is to give an overview of the Nuclear Science User Facilities (NSUF) and its materials acquisition routes, sample library, and concrete related awards, at the NRC-NEA Hybrid Workshop on International Concrete Harvesting .
Diffusion Behavior of Lanthanide Fission Products in bcc Fe Cladding: A First-Principles Study
Fuel-cladding chemical interaction poses significant challenges in nuclear reactors, where fission products from nuclear fuel interact with Fe-based cladding materials, potentially compromising their structural integrity. This study investigates the diffusion behavior of oversized fission products, Lanthanum (La), Cerium (Ce), Praseodymium (Pr), Neodymium (Nd), within body-centered cubic Fe cladding using the density functional theory, nudged elastic […]
Role of Nuclear Science User Facilities (NSUF) in Nuclear Energy Materials Research
The Nuclear Science User Facilities (NSUF) is one of a diverse number of U.S. Department of Energy (DOE) user facilities established to provide researchers with the most advanced tools of modern science. The NSUF is unique and represents a consortium of capabilities distributed across the U.S. at twenty-one institutions. The NSUF is centered at and […]
Advanced Characterization Capabilities for Nuclear Materials via Nuclear Science User Facilities (NSUF)
Advanced post-irradiation examination (PIE) techniques are required to design new or improved nuclear materials, characterize, and understand in-core behavior of fuel and materials, and support the qualification of new reactor materials. The Nuclear Science User Facilities (NSUF) is the U.S. Department of Energy Office of Nuclear Energy’s only designated nuclear science user facility. NSUF provides […]
Empirical validation of size effects in sub-sized tensile specimens for nuclear structural materials
Advancing the understanding of material behavior and phenomena related to the size effect in small-scale components is important for settings where limited quantities of material samples can be tested. Through research and collaborative efforts, the scientific community and industry stakeholders have established guidelines for sub-sized specimen testing, encompassing best practices for specimen preparation, testing equipment, […]