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


Electrochemical study of the dissolution of oxide films grown on type 316L stainless steel in molten fluoride salt
Qiu, J., Macdonald, D. D., Schoell, R., Han, J., Mastromarino, S., Scully, J. R., … Hosemann, P. (2021), CORROSION SCIENCE.
Helium bubble nucleation and growth in alloy HT9 through the use of in situ TEM: Sequential he-implantation and heavy-ion irradiation versus dual-beam irradiation
Duemmler, K., Zheng, C., Baumier, C., Gentils, A., & Kaoumi, D. (2021), JOURNAL OF NUCLEAR MATERIALS, 545.
A new mechanism for void-cascade interaction from nondestructive depth-resolved atomic-scale measurements of ion irradiation-induced defects in Fe
Agarwal, S., Liedke, M. O., Jones, A. C. L., Reed, E., Kohnert, A. A., Uberuaga, B. P., … Selim, F. A. (2020), SCIENCE ADVANCES, 6(31).
An Electrochemical Impedance Spectroscopic Study of Oxide Films in Liquid Metal
Qiu, J., Macdonald, D. D., Li, N., Schoell, R., Kaoumi, D., & Hosemann, P. (2020), JOM.
Detecting and imaging stress corrosion cracking in stainless steel, with application to inspecting storage canisters for spent nuclear fuel
Remillieux, M. C., Kaoumi, D., Ohara, Y., Geesey, M. A. S., Xi, L., Schoell, R., … Shayer, Z. (2020), NDT & E INTERNATIONAL, 109.
Dislocation loop evolution in F/M steel T91 under in-situ ion irradiation: Influence of the presence of initial dislocations
Zheng, C., & Kaoumi, D. (2020), JOURNAL OF NUCLEAR MATERIALS, 540.
Effect of heterostructure and hetero-deformation induced hardening on the strength and ductility of brass
Fang, X. T., He, G. Z., Zheng, C., Ma, X. L., Kaoumi, D., Li, Y. S., & Zhu, Y. T. (2020), ACTA MATERIALIA, 186, 644–655.
Electrical properties of thermal oxide scales on pure iron in liquid lead-bismuth eutectic
Qiu, J., Han, J., Schoell, R., Popovic, M., Ghanbari, E., Kaoumi, D., … Hosemann, P. (2020), CORROSION SCIENCE, 176.
In Situ Micropillar Compression Tests of 304 Stainless Steels After Ion Irradiation and Helium Implantation
Schoell, R., Frazer, D., Zheng, C., Hosemann, P., & Kaoumi, D. (2020), JOM.
In situ synchrotron X-ray tomography of 304 stainless steels undergoing chlorine-induced stress corrosion cracking
Schoell, R., Xi, L., Zhao, Y., Wu, X., Yu, Z., Kenesei, P., … Kaoumi, D. (2020), CORROSION SCIENCE, 170.

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