Djamel Kaoumi

Associate Professor of Nuclear Engineering

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.


PhD 2007

Nuclear Engineering

Pensylvania State University

MS 2001

Nuclear Engineering and minor in Materials Science

University of Florida

BS 1999


Institut National Polytechnique de Grenoble (France)

Research Description

Irradiation effects in structural and cladding materials Mechanical behavior of alloys / alloy development Corrosion and Stress Corrosion Cracking of structural alloys


Correlation of in-situ transmission electron microscopy and microchemistry analysis of radiation-induced precipitation and segregation in ion irradiated advanced ferritic/martensitic steels
Zheng, C., Ke, J.-H., Maloy, S. A., & Kaoumi, D. (2019), SCRIPTA MATERIALIA, 162, 460–464.
Environmental effect on mechanical properties of a gamma-prime strengthened nickel-based alloy: Effect of the surface oxidation and formation of gamma-prime free zones
Insights into the plastic behavior of irradiated Ni-based alloy through in-situ TEM experiments: Formation and evolution of defect-free channels
Kaoumi, D., & Jammot, V. (2019), JOURNAL OF NUCLEAR MATERIALS, 523, 33–42.
Interplay Between Grain Boundaries and Radiation Damage
Barr, C. M., El-Atwani, O., Kaoumi, D., & Hattar, K. (2019, April), JOM.
Ion irradiation effects on commercial PH 13-8 Mo maraging steel Corrax
Zheng, C., Schoell, R., Hosemann, P., & Kaoumi, D. (2019), JOURNAL OF NUCLEAR MATERIALS, 514, 255–265.
Microstructure response of ferritic/martensitic steel HT9 after neutron irradiation: effect of dose
Zheng, C., Reese, E. R., Field, K. G., Marquis, E., Maloy, S. A., & Kaoumi, D. (2019), JOURNAL OF NUCLEAR MATERIALS, 523, 421–433.
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.

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