Djamel Kaoumi

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.

Multi-length scale characterization of point defects in thermally oxidized, proton irradiated iron oxides

MATERIALIA, 28.

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.

<p>The mechanism behind the high radiation tolerance of Fe-Cr alloys</p>

JOURNAL OF APPLIED PHYSICS, 131(12).

A multimodal approach to revisiting oxidation defects in Cr2O3

NPJ MATERIALS DEGRADATION, 6(1).

Achieving high hetero-deformation induced (HDI) strengthening and hardening in brass by dual heterostructures

Fang, X. T., Li, Z. K., Wang, Y. F., Ruiz, M., Ma, X. L., Wang, H. Y., … Zhu, Y. T. (2022, January 30).

Corrosion behavior of a series of combinatorial physical vapor deposition coatings on SiC in a simulated boiling water reactor environment

JOURNAL OF NUCLEAR MATERIALS, 572.

Effect of thermal oxidation on helium implanted 316L stainless steel

JOURNAL OF APPLIED PHYSICS, 132(18).

Investigation of the fatigue crack behavior of 304 stainless steels using synchrotron X-ray tomography and diffraction: Influence of the martensite fraction and role of inclusions

MATERIALS CHARACTERIZATION, 188.

Laser Powder Bed Fusion Additive Manufacturing of Oxide Dispersion Strengthened Steel Using Gas Atomized Reaction Synthesis Powder

SSRN. http://www.scopus.com/inward/record.url?eid=2-s2.0-85127703398&partnerID=MN8TOARS

Laser Powder Bed Fusion of ODS 14YWT from Gas Atomization Reaction Synthesis Precursor Powders

Saptarshi, S., DeJong, M., Rock, C., Anderson, I., Napolitano, R., Forrester, J., … Horn, T. (2022, August 2). JOM, Vol. 8.

Laser powder bed fusion additive manufacturing of oxide dispersion strengthened steel using gas atomized reaction synthesis powder

MATERIALS & DESIGN, 216.

Mechanism of chlorine-induced stress corrosion cracking of two 304 SS heats in simulated marine environment through in situ X-ray tomography and diffraction: Role of deformation induced martensite and crack branching

MATERIALS CHARACTERIZATION, 190.

Spark Plasma Sintered Monbti Based Multi Principal Element Alloys with Cr, V, and Zr

SSRN. http://www.scopus.com/inward/record.url?eid=2-s2.0-85130733691&partnerID=MN8TOARS

Spark plasma sintered, MoNbTi-based multi-principal element alloys with Cr, V, and Zr

JOURNAL OF ALLOYS AND COMPOUNDS, 927.

Surprisingly high irradiation-induced defect mobility in Fe3O4 as revealed through in situ transmission electron microscopy

MATERIALS CHARACTERIZATION, 187.

Synthesis of Nano-Oxide Precipitates by Implantation of Ti, Y and O Ions in Fe-10%Cr: Towards an Understanding of Precipitation in Oxide Dispersion-Strengthened (ODS) Steels

MATERIALS, 15(14).

Creep properties of advanced austenitic steel 709 determined through short experiments under in-situ neutron diffraction followed by TEM characterization

MATERIALS CHARACTERIZATION, 182.

Electrochemical study of the dissolution of oxide films grown on type 316L stainless steel in molten fluoride salt

CORROSION SCIENCE, 186.

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).

A pathway to synthesizing single-crystal Fe and FeCr films

Surface and Coatings Technology, 403.

Achieving High Hetero-Deformation Induced (HDI) Strengthening and Hardening in Brass by Dual Heterostructures

SSRN.

An Electrochemical Impedance Spectroscopic Study of Oxide Films in Liquid Metal

JOM, 72(5), 2082–2088.

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.

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

ArXiv.

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

JOM, 72(7), 2778–2785.

In situ TEM investigation of irradiation induced amorphization of fe oxide

Microscopy and Microanalysis.

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.

Interface characterization of candidate dual-purpose barrier coatings for SiC/SiC accident tolerant fuel cladding

19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, EnvDeg 2019, 1043–1051. http://www.scopus.com/inward/record.url?eid=2-s2.0-85080034549&partnerID=MN8TOARS

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 AND 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.

Integrated research program overview on the “innovative approaches to marine atmospheric stress corrosion cracking inspection, evaluation and modeling in used-fuel dry storage canisters”

Integrated research program overview on the “innovative approaches to marine atmospheric stress corrosion cracking inspection, evaluation and modeling in used-fuel dry storage canisters.” In Ceramic Transactions (Vol. 262, pp. 151–164). http://www.scopus.com/inward/record.url?eid=2-s2.0-85055490485&partnerID=MN8TOARS

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

Byun, T. S., Kaoumi, D., & Bai, X.-M. (2017, December 15). JOURNAL OF NUCLEAR MATERIALS, Vol. 497, pp. 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 AND 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 AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 677, 474–484.

In-situ ion irradiation of ZIRLO^® alloy

Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance, 417–424. http://www.scopus.com/inward/record.url?eid=2-s2.0-85019028888&partnerID=MN8TOARS

Tensile behavior of inconel X750 Sheets: Effect of heat treatment

Transactions of the American Nuclear Society, 115, 469–472. http://www.scopus.com/inward/record.url?eid=2-s2.0-85029410263&partnerID=MN8TOARS

Characterization of microstructure and property evolution in advanced cladding and duct: Materials exposed to high dose and elevated temperature

Journal of Materials Research, 30(9), 1246–1274.

Deformation induced martensitic transformation in 304 ss

PTM 2015 - Proceedings of the International Conference on Solid-Solid Phase Transformations in Inorganic Materials 2015, 629–630. http://www.scopus.com/inward/record.url?eid=2-s2.0-84962758624&partnerID=MN8TOARS

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.

Introduction

Journal of Materials Research, 30(9), 1157.

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.

Precipitate characterization in two ODS steels using synchrotron XRD of consolidated samples and Cu-Kα XRD of precipitate extractions

Transactions of the American Nuclear Society, 109(PART 1), 576–579. http://www.scopus.com/inward/record.url?eid=2-s2.0-84902780874&partnerID=MN8TOARS

Tensile behavior of inconel 617 vs. Haynes 230: Effects of temperature and strain rate

Transactions of the American Nuclear Society, 109(PART 1), 644–647. http://www.scopus.com/inward/record.url?eid=2-s2.0-84902821147&partnerID=MN8TOARS

Friction consolidation of an oxide dispersion strengthened steel

Transactions of the American Nuclear Society, 107, 458–461. http://www.scopus.com/inward/record.url?eid=2-s2.0-84876557879&partnerID=MN8TOARS

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.

Characterization and in-situ ion-irradiation of MA957 ODS steel

Transactions of the American Nuclear Society, 98, 1113–1114. http://www.scopus.com/inward/record.url?eid=2-s2.0-55249124982&partnerID=MN8TOARS

Grain growth in nanocrystalline metal thin films under in situ ion-beam irradiation

ASTM Special Technical Publication, 1492 STP, 206–218. http://www.scopus.com/inward/record.url?eid=2-s2.0-62849116960&partnerID=MN8TOARS

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 nanocrystalline metal thin films under in situ ion-beam irradiation

Journal of ASTM International, 4(8).

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.

Irradiation-enhanced second-phase precipitation in Zr-Fe nanocrystalline thin films

Materials Research Society Symposium Proceedings, 908, 7–12.