Associate Professor of Nuclear Engineering
- Burlington Laboratory 2115
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Dr. Kaoumi’s research interests revolve around developing a mechanistic understanding of microstructure property relationships in nuclear materials, with an emphasis on microstructure evolution under harsh environment (i.e. irradiation, high temperature, and mechanical stress) and how it can impact the macroscopic properties and performance. Understanding the basic mechanisms of degradation of materials at the nanostructure level is necessary for the development of predictive models of the materials performance and for the design and development of better materials. Materials of interest include advanced alloys for structural and cladding applications in advanced nuclear systems (e.g. Austenitic steels , Advanced Ferritic/Martensitic Steels, Oxide-Dispersion-Strengthened (ODS) Steels), High-temperature Ni-based alloys, Zirconium alloys and nanocrystalline metallic systems. Characterization techniques of predilection include both in-situ and ex-situ techniques e.g. In-situ irradiation in TEM (over 15 years of experience), In-situ straining in a TEM, chemi-STEM, SEM, XRD, Synchrotron XRD.
Pensylvania State University
Nuclear Engineering and minor in Materials Science
University of Florida
Institut National Polytechnique de Grenoble (France)
Irradiation effects in structural and cladding materials Mechanical behavior of alloys / alloy development Corrosion and Stress Corrosion Cracking of structural alloys
- Deformation induced martensitic transformation in 304 austenitic stainless 1 steel: In-situ vs. ex-situ transmission electron microscopy characterization
- Kaoumi, D., & Liu, J. L. (2018), Materials Science & Engineering. A, Structural Materials: Properties, Microstructure and Processing, 715, 73–82.
- Use of in-situ TEM to characterize the deformation-induced martensitic transformation in 304 stainless steel at cryogenic temperature
- Liu, J., & Kaoumi, D. (2018), Materials Characterization, 136, 331–336.
- Microstructural processes in irradiated materials
- Byun, T. S., Kaoumi, D., & Bai, X. M. (2017), Journal of Nuclear Materials, 497, 107–107.
- Radiation induced segregation and precipitation behavior in self-ion irradiated Ferritic/Martensitic HT9 steel
- Zheng, C., Auger, M. A., Moody, M. P., & Kaoumi, D. (2017), Journal of Nuclear Materials, 491, 162–176.
- Radiation-induced swelling and radiation-induced segregation & precipitation in dual beam irradiated Ferritic/Martensitic HT9 steel
- Zheng, C., & Kaoumi, D. (2017). Radiation-induced swelling and radiation-induced segregation & precipitation in dual beam irradiated Ferritic/Martensitic HT9 steel. Materials Characterization, 134, 152–162,
- Serrated tensile flow in inconel X750 sheets: Effect of heat treatment
- Marsh, C., & Kaoumi, D. (2017), Materials Science & Engineering. A, Structural Materials: Properties, Microstructure and Processing, 707, 136–147.
- Effect of heat treatment on the temperature dependence of the fracture behavior of X-750 alloy
- Marsh, C., Depinoy, S., & Kaoumi, D. (2016), Materials Science & Engineering. A, Structural Materials: Properties, Microstructure and Processing, 677, 474–484.