Djamel Kaoumi

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

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

SCIENCE ADVANCES, 6(31).

An Electrochemical Impedance Spectroscopic Study of Oxide Films in Liquid Metal

JOM.

Detecting and imaging stress corrosion cracking in stainless steel, with application to inspecting storage canisters for spent nuclear fuel

NDT & E INTERNATIONAL, 109.

Dislocation loop evolution in F/M steel T91 under in-situ ion irradiation: Influence of the presence of initial dislocations

JOURNAL OF NUCLEAR MATERIALS, 540.

Effect of heterostructure and hetero-deformation induced hardening on the strength and ductility of brass

ACTA MATERIALIA, 186, 644–655.

Electrical properties of thermal oxide scales on pure iron in liquid lead-bismuth eutectic

CORROSION SCIENCE, 176.

In Situ Micropillar Compression Tests of 304 Stainless Steels After Ion Irradiation and Helium Implantation

JOM.

In situ synchrotron X-ray tomography of 304 stainless steels undergoing chlorine-induced stress corrosion cracking

CORROSION SCIENCE, 170.

Microstructure response of ferritic/martensitic steel HT9 after neutron irradiation: Effect of temperature

JOURNAL OF NUCLEAR MATERIALS, 528.

Tensile behavior and microstructural evolution of a Fe-25Ni-20Cr austenitic stainless steel (alloy 709) from room to elevated temperatures through in-situ synchrotron X-ray diffraction characterization and transmission electron microscopy

JOURNAL OF NUCLEAR MATERIALS, 540.

Correlation of in-situ transmission electron microscopy and microchemistry analysis of radiation-induced precipitation and segregation in ion irradiated advanced ferritic/martensitic steels

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

MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 752, 136–144.

Insights into the plastic behavior of irradiated Ni-based alloy through in-situ TEM experiments: Formation and evolution of defect-free channels

JOURNAL OF NUCLEAR MATERIALS, 523, 33–42.

Interplay Between Grain Boundaries and Radiation Damage

[Review of ]. JOM, 71(4), 1233–1244.

Ion irradiation effects on commercial PH 13-8 Mo maraging steel Corrax

JOURNAL OF NUCLEAR MATERIALS, 514, 255–265.

Microstructure response of ferritic/martensitic steel HT9 after neutron irradiation: effect of dose

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

Materials Science & Engineering. A, Structural Materials: Properties, Microstructure and Processing, 715, 73–82.

Effect of dose on irradiation-induced loop density and Burgers vector in ion-irradiated ferritic/martensitic steel HT9

Philosophical Magazine, 98(26), 2440–2456.

Use of in-situ TEM to characterize the deformation-induced martensitic transformation in 304 stainless steel at cryogenic temperature

Materials Characterization, 136, 331–336.

Microstructural and Nanomechanical Characterization of In-Situ He Implanted and Irradiated fcc Materials

Microscopy and Microanalysis, 23(S1), 756–757.

Microstructural processes in irradiated materials

Journal of Nuclear Materials, 497, 107–107.

Microstructure Characterization of Ion-irradiated Ferritic/Martensitic HT9 Steel

Microscopy and Microanalysis, 23(S1), 2214–2215.

Radiation induced segregation and precipitation behavior in self-ion irradiated Ferritic/Martensitic HT9 steel

Journal of Nuclear Materials, 491, 162–176.

Radiation-induced swelling and radiation-induced segregation & precipitation in dual beam irradiated Ferritic/Martensitic HT9 steel

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

Materials Science & Engineering. A, Structural Materials: Properties, Microstructure and Processing, 707, 136–147.

A high temperature mechanical study on PH 13-8 Mo maraging steel

Materials Science and Engineering: A, 651, 574–582.

Effect of heat treatment on the temperature dependence of the fracture behavior of X-750 alloy

Materials Science & Engineering. A, Structural Materials: Properties, Microstructure and Processing, 677, 474–484.

Dispersoid Distribution and Microstructure in Fe-Cr-Al Ferritic Oxide Dispersion-Strengthened Alloy Prepared by Friction Consolidation

Metallurgical and Materials Transactions A, 46(10), 4730–4739.

Microstructural evolution in NF616 (P92) and Fe–9Cr–0.1C-model alloy under heavy ion irradiation

Journal of Nuclear Materials, 466, 179–186.

Small-Scale Mechanical Testing on Proton Beam-Irradiated 304 SS from Room Temperature to Reactor Operation Temperature

JOM, 67(12), 2959–2964.

Using In-Situ TEM to Characterize the Microstructure Evolution of Metallic Systems under External Solicitation

Microscopy and Microanalysis, 21(S3), 111–112.

Microstructure evolution of two model ferritic/martensitic steels under in situ ion irradiation at low doses (0–2dpa)

Journal of Nuclear Materials, 445(1-3), 12–19.

Self-ordered defect structures in two model F/M steels under in situ ion irradiation

Journal of Nuclear Materials, 448(1-3), 233–238.

Tensile deformation behavior and microstructure evolution of Ni-based superalloy 617

Journal of Nuclear Materials, 454(1-3), 265–273.

Tensile deformation behavior of a nickel based superalloy at different temperatures

Materials Science and Engineering: A, 599, 196–203.

Friction Consolidation of MA956 powder

Journal of Nuclear Materials, 442(1-3), S112–S118.

In Situ TEM Studies of Microstructure Evolution Under Ion Irradiation for Nuclear Engineering Applications

Microscopy and Microanalysis, 16(S2), 1606–1607.

In situ transmission electron microscopy and ion irradiation of ferritic materials

Microscopy Research and Technique, 72(3), 182–186.

TEM Characterization of Crept and Irradiated Nano-structured Ferritic Alloys

Microscopy and Microanalysis, 15(S2), 1350–1351.

A thermal spike model of grain growth under irradiation

Journal of Applied Physics, 104(7), 073525.

Influence of alloying elements on grain-growth in Zr(Fe) and Cu(Fe) thin-films under in situ ion-irradiation

Journal of Nuclear Materials, 382(2-3), 184–189.

Grain growth in Zr–Fe thin films during in situ ion irradiation in a TEM

Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 242(1-2), 490–493.