Djamel Kaoumi
Associate Professor of Nuclear Engineering
- Phone: 919.515.2046
- Email: dkaoumi@ncsu.edu
- Office: Burlington Laboratory 2115
- Website: https://www.ne.ncsu.edu/nuclearmaterials/
Prof Djamel Kaoumi received his Ph.D. in Nuclear Engineering from Pennsylvania State University in 2007 and his Masters of Science from the University of Florida in 2001 with a minor in Materials Science and Engineering. Prior to this, he received his Diplome d’Ingenieur from the Institut Polytechnique National de Grenoble in France in 2000 and his BSc in Physics from the same French institute in 1999.
Prof. 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 environments (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 developing predictive models of the material’s performance and the design and development of better materials.
Throughout his academic journey, Prof Kaoumi has taught classes on “Introduction to Nuclear Materials”, “Radiation Damage”, and “Radiation detection and measurement” to a diverse mix of students with different backgrounds and different majors (Nuclear Engineering, Materials Science and Engineering, Mechanical Engineering) and he has been mentoring students from different backgrounds.
Research Description
- Alloy Development for Nuclear Applications, particularly structural and cladding applications, through powder metallurgy: ODS Ni-based alloys for Molten Salt Reactor, ODS steels for Fusion applications Refractory Alloys for Gen IV reactors in general. Amoong processing routes, Additive Manufacturing is primarily used.
- Effects of Irradiation on microstructure, on mechanical properties through the use of ion irradiation, and more particularly in-situ ion irradiation in the TEM.
- Corrosion studies in Light Water Reactor simulated water chemistry using pressurized water autoclaves available in Prof Kaoumi’s lab.
- Coupled effects of irradiation and corrosion on alloys of interest for Gen IV reactor (Molten Salt environment and Liquid Metal cooled reactors).
- Mechanical behavior of advanced alloys through in situ testing the TEM, and under the synchrotron X-Ray beam, in complement to ex-situ bulk mechanical testing. 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. Prof Kaoumi has built extensive expertise for in-situ experiments done in a Transmission Electron Microscope (TEM) which include In-situ ion-irradiation and In-situ straining and mechanical testing experiments. His expertise and contribution to understanding the microstructure evolution under irradiation/stress/temperature through in-situ characterization have earned Prof Kaoumi more than 45 invited talks/seminars related to this scope of his research.
Education
| Degree | Program | School | Year |
|---|---|---|---|
| Ph.D. | Doctorate of Philosophy in Nuclear Engineering | Cornell University | 2007 |
| MSNE | Masters of Science in Materials Sciences | University of Florida | 2001 |
| BS.Phy. | Bachelors of Science in Physics | Institut National Polytechnique de Grenoble (France) | 1999 |
Publications
- Effect of cryogenic milling on the mechanical and corrosion properties of ODS Hastelloy-N
- Hong, M., Bickel, J. E., Demir, E., Kaoumi, D., & Hosemann, P. (2024), MATERIALIA, 37. https://doi.org/10.1016/j.mtla.2024.102215
- Effect of irradiation on the corrosion of 304 stainless steel in pressurized water reactor (PWR) simulated water chemistry
- Tsai, F.-Y., Schoell, R., Hattar, K., & Kaoumi, D. (2024), CORROSION SCIENCE, 240. https://doi.org/10.1016/j.corsci.2024.112454
- Effect of thermal oxidation on helium implanted pure iron
- Hong, M., deJong, M., Balooch, M., Kaoumi, D., & Hosemann, P. (2025), Journal of Nuclear Materials. https://doi.org/10.1016/j.jnucmat.2024.155377
- MICROSTRUCTURAL AND TENSILE PROPERTY DIFFERENCES BETWEEN Ni-16Mo AND ODS ALLOYS FABRICATED BY THE POWDER METALLURGY PROCESSES
- Bae, J., Lee, S., Chang, K., Kaoumi, D., & Noh, S. (2024), ARCHIVES OF METALLURGY AND MATERIALS, 69(2), 421–424. https://doi.org/10.24425/amm.2024.149758
- Review of Solid-State Consolidation Processing Techniques of ODS Steels (Hot Extrusion, Hot Isostatic Pressing, Spark Plasma Sintering, and Stir Friction Consolidation): Resulting Microstructures and Mechanical Properties
- Dejong, M., Horn, T., & Kaoumi, D. (2024, October 10), JOM, Vol. 10. https://doi.org/10.1007/s11837-024-06853-3
- The self-annealing of irradiation induced defects in magnetite Fe3O4: Revealing reversible irradiation-induced disorder transformation through in situ TEM
- Morales, A. M. L., Chen, W.-Y., & Kaoumi, D. (2024), JOURNAL OF APPLIED PHYSICS, 136(7). https://doi.org/10.1063/5.0226606
- Designing Nuclear Fuels with a Multi-Principal Element Alloying Approach
- Beausoleil, G., Zillinger, J., Hawkins, L., Yao, T., Weiss, A. G., Pu, X., … Kaoumi, D. (2023, September 20), NUCLEAR TECHNOLOGY, Vol. 9. https://doi.org/10.1080/00295450.2023.2236796
- Multi-length scale characterization of point defects in thermally oxidized, proton irradiated iron oxides
- Chan, H. L., Auguste, R., Romanovskaia, E., Morales, A. L., Schmidt, F., Romanovski, V., … Scully, J. R. (2023), MATERIALIA, 28. https://doi.org/10.1016/j.mtla.2023.101762
- Multi-length scale characterization of point defects in thermally oxidized, proton irradiated iron oxides (vol 28, 101762, 2023)
- Chan, H. L., Auguste, R., Romanovskaia, E., Morales, A. L., Liedke, M. O., Schmidt, F., … Scully, J. R. (2023, September), MATERIALIA, Vol. 31. https://doi.org/10.1016/j.mtla.2023.101868
- The mechanism behind the high radiation tolerance of Fe-Cr alloys
- Agarwal, S., Butterling, M., Liedke, M. O., Yano, K. H., Schreiber, D. K., Jones, A. C. L., … Selim, F. A. (2022), JOURNAL OF APPLIED PHYSICS, 131(12). https://doi.org/10.1063/5.0085086
