Menu:
Research Projects
Current Research Projects in 2024
Mechanisms-based Acceleration of Materials Qualifications for Creep-Fatigue Performance in Advanced Nuclear Systems |
| This project aims to quantify and model creep-fatigue damage under different loading patterns, temperatures, and microstructural changes. A mechanism-based approach for analyzing creep-fatigue in high temperature alloys enable evaluation creep-fatigue resistance in advanced nuclear systems. |
Microstructural and Mechanical Property Characterization of Dffusion Bonding for Compact Heat Exchanger |
| The project aims to improve the diffusion bonding process of alloys like Alloy 617 and 316H Stainless Steel for high-temperature nuclear applications, and to define acceptance standards for their performance throughout their service life. |
Utilizing Additive Manufacturing to Improve Materials Designed for Extreme Environments Alloys |
| Printed 316H tensile samples of different printing orientations and compared the tensile values to a wrought 316H sample. EBSD shows different grain patterns for normal to build direction and along the build direction. A |
Microstructual Characterization and Mechanical Property Investigation of Neutron Irradiated Ferritic Alloys |
| For lower-temperature high-dose components, ferritic-martensitic steels including oxide dispersion-strengthened (ODS) alloys, offer potential solutions; however, they require extensive R&D to understand their radiation damage characteristics and mechanical properties. Various techniques including TEM (Transmission Electron Microscopy), XRD (X-ray Diffraction), APT (Atom Probe Tomography), and PAS (Positron Annihilation Spectroscopy) are used to investigate the microstructure and mehcanical property of ferritic alloys |
Understanding Hydrogen Effects in Austenitic Steels for use in Hydrogen-Facing Applications |
| Austenitic stainless steels are widely used for the transportation/storage of hydrogen in the hydrogen energy system. Research has been performed on several austenitic steel alloys by substituting Ni to examine the impact of hydrogen on elasticity, plasticitiy and hydrogen-related failure. |
Corrosion Assesment on Liquid Metals |
| The utilization of liquid metals in nuclear reactors is an innovative technology. Research includes the thermo-physical characteristics of various mixture of liquid metals and the corrosion behavior of liquid-facing components. Furthermore, the effects of corrosion on mechanical degradation have been investigated. |
Past Research Projects |
| Oxygen Sensors in Lead-Bismuth Eutectic |
| Fatigue/Creep-Fatigue Behavior of Copper Alloys for High Heat Flux Applications |
| Material Properties Testing of ITER First Wall Components |
| The Effect of Localized Flow on Fracture of Reactor Components |
| Microstructural Evolution of Nuclear Fuel Under Irradiation |
| Irradiation-induced microstructural evolution and mechanical properties in iron-chromium |
| Using Impedance Spectroscopy to Monitor Lead-Bismuth Corrosion |
| Development of Austenitic ODS Alloys for Very High Temperature Applications (2011 to 2014) |
| Fundamental Studies of Irradiation-induced Modifications in Microstructural Evolution and Mechanical Properties of Advanced Alloys (2014 to 2017) |
| Investigation of High Temperature Mechanical Behavior of Alloy 709 for Advanced Fast Reactor Applications |