Influence of microstructural parameters on the mechanical properties of oxide dispersion strengthened Fe-14Cr steels

M Dadé, J Malaplate, J Garnier, F De Geuser… - Acta Materialia, 2017 - Elsevier
The effect of microstructural parameters on the microstructure, tensile properties from room
temperature to 800° C and creep properties at 650° C has been investigated in a 14% Cr …

Review of Solid-State Consolidation Processing Techniques of ODS Steels (Hot Extrusion, Hot Isostatic Pressing, Spark Plasma Sintering, and Stir Friction …

M deJong, T Horn, D Kaoumi - JOM, 2024 - Springer
This paper reviews the solid-state consolidation processing techniques for oxide dispersion
strengthened steels and compares them in terms of the resulting microstructure and reported …

ODS Ferritic/martensitic alloys for Sodium Fast Reactor fuel pin cladding

P Dubuisson, Y de Carlan, V Garat, M Blat - Journal of Nuclear Materials, 2012 - Elsevier
The development of ODS materials for the cladding for Sodium Fast Reactors is a key issue
to achieve the objectives required for the GEN IV reactors. CEA, AREVA and EDF have …

Microstructure characterization and strengthening mechanisms of oxide dispersion strengthened (ODS) Fe-9% Cr and Fe-14% Cr extruded bars

A Chauhan, F Bergner, A Etienne, J Aktaa… - Journal of Nuclear …, 2017 - Elsevier
The collaborative study is focused on the relationship between microstructure and yield
stress for an ODS Fe-9% Cr-based transformable alloy and an ODS Fe-14% Cr-based …

Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part II—Mechanistic models and predictions

JH Kim, TS Byun, DT Hoelzer, CH Park… - Materials Science and …, 2013 - Elsevier
The temperature dependence of strengthening mechanisms in the nanocluster-
strengthened 14YWT alloy was investigated to elucidate the relative significance of …

Oxide dispersion-strengthened/ferrite-martensite steels as core materials for Generation IV nuclear reactors

S Ukai, S Ohtsuka, T Kaito, Y De Carlan, J Ribis… - Structural materials for …, 2017 - Elsevier
Oxide dispersion-strengthened (ODS) steels are the most promising candidate materials for
fuel cladding of Generation IV nuclear reactors. The progress and current status for …

[HTML][HTML] Development of oxide dispersion strengthened ferritic steel with enhanced strength–ductility combination through dispersion strengthening and back stress …

Y Zhang, B Liu, R Zhang, H Liu, Y Cao, J Li… - Journal of Materials …, 2023 - Elsevier
Oxide dispersion strengthened (ODS) ferritic steel is a potential structural material for fast
neutron reactor and fusion reactor application. In this study, a new Fe–13Cr–2W-0.4 Ti-0.6 …

Microstructure and texture evolution and ring-tensile properties of recrystallized FeCrAl ODS cladding tubes

SMS Aghamiri, T Sowa, S Ukai, N Oono… - Materials Science and …, 2020 - Elsevier
Oxide dispersion strengthened (ODS) FeCrAl ferritic steels are being developed as potential
accident tolerance fuel cladding materials for the light water reactors (LWRs) due to …

Study of the deformation mechanisms in a Fe–14% Cr ODS alloy

M Praud, F Mompiou, J Malaplate, D Caillard… - Journal of Nuclear …, 2012 - Elsevier
In this present work, the plasticity of a rod bar of a 14% Cr ferritic ODS steel is examined
through a multiscale approach based on both macroscopic and microscopic results. This bar …

Microstructure and mechanical properties of thin-walled ODS ferritic steel tubes fabricated by a near-net forming method

Y Zhang, B Liu, Y Cao, R Zhang, J Li, Q Fang… - Materials Science and …, 2024 - Elsevier
This research successfully applied a new near-net forming process for producing thin-walled
ODS ferritic steel tubes. The process involves hot isostatic pressing (HIP), hot extrusion (HE) …