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Showing 1 to 17 of 17 for “"Ferritic/martensitic"”.
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Tensile Fracture Mechanisms of Ferritic/martensitic Structural Materials
X-ray measurements and analysis not only support the hypothesis of the association between critical stress and critical interfacial strength, but also offer a new method to determine the true strain/stress behavior during deformation. This method is called the Universal Micro-structural …
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Microstructure Evolution of Two Model Ferritic/Martensitic Steels Under Ion Irradiation In A Transmission Electron Microscope
<p>Ferritic/martensitic steels are candidate materials for structural and cladding components designed for Generation IV reactors because of their superior resistance to radiation damage at the high operating temperatures envisioned in these reactors. To enable the development and optimization of …
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Role of nitrogen in the structure and properties of proton irradiated 12Cr1MoWV ferritic/martensitic steel for advanced nuclear reactor cores, The
The 12Cr1MoWV (wt%) ferritic/martensitic steel HT9 is a candidate material for fuel cladding in advanced nuclear reactors, such as the Versatile Test Reactor, currently under development. As such, understanding the relationship between microstructure and mechanical properties in the context of …
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The relationship between mechanical properties and microstructure of HT9 steel
… and corrosion from liquid metal coolants. HT9, a ferritic/martensitic alloy, was used in previous fast research reactors (such as EBR-II and FFTF). However, it needs validation before it can be selected for use in the more extreme environments of Gen–IV reactors. This dissertation presents a …
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The effects of nitrogen and nickel on the microstructure and mechanical properties of 16 wt.% chromium stainless steels
… of experimental 16 wt.% chromium dual-phase ferritic-martensitic stainless steels. A comparison was made between an alloy containing 2.5 wt.% nickel (low interstitial content [C + N = 0.03 wt%]), and three alloys possessing low nickel (0 - 1 wt.%) and high nitrogen contents (0.06 - 0.12 …
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New developments in steel reinforcement protection from corrosion
… (3M Skotchkot 426) and the recent Dual Phase Ferritic Martensitic bars (MMFXI/II steels) have emerged. This study describes each new reinforcement protection technology and compares them through cost, service life, availability and resistance considerations. The comparisons show that …
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Advanced characterization of the early-stage evolution of microstructures and mechanical properties in neutron-irradiated commercial steels
… and mechanical properties of two types of Fe-Cr ferritic-martensitic (F-M) steels, HT9 and T91, were characterized. The materials were irradiated in the Advanced Test Reactor (ATR) at different temperatures and neutron fluences. Three temperature ranges and four neutron dose levels were …
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Radiation-induced microstructural and mechanical property modifications in advanced alloys
… austenitic steel Alloy 709, Fe–9Cr ferritic/martensitic steel T91, and Fe–14Cr ferritic ODS steel MA957, were investigated using a combination of microstructure characterizations and nanoindentation measurements. Several different types of irradiation, including ex situ bulk ion …
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Alloy Design for a Fusion Power Plant
… of a set of candidate alloys, reduced-activation ferritic-martensitic steels. The models have been compared to other methods, and it is demonstrated that a neural network approach to modelling the properties of irradiated steels provides a useful tool in the future engineering of fusion materials, …
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Characterization of bending fatigue mini-specimens for nuclear materials
… were made of austenitic SS304, SS316, HT9 ferritic martensitic steel, and Incoloy alloy MA956 oxide dispersion strengthens (ODS). A comparison between the mini-specimens and the standard specimen ASTM B593 had similar design but a smaller size. The bending fatigue machine VSS-40H was …
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Mechanical properties of materials for fusion power plants
… and yield strength of various low{activation ferritic/ martensitic steels were modelled by neural networks and Gaussian processes. These models were used to make predictions which were compared to exper- imental values. Combined with other techniques and thermodynamic tools, it was possible to …
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Study of microstructure evolution in F/M steel T91 by in-situ synchrotron wide-angle X-rays scattering
T91 ferritic-martensitic (F/M) steel is one of the leading candidates for high temperature structural materials in advanced nuclear power applications. In situ Wide-angle X-ray Scattering (WAXS) was used to investigate T91 during tensile test under 3 different temperatures: room temperature (RT), …
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Continuum Damage Mechanics (CDM) modelling of dislocation creep in 9-12% Cr creep resistant steels
… for these applications are in the family of ferritic/martensitic 9-12% Cr steels chosen for their superior material properties especially during long-term exposure as coal fired power plants typically operate for over 20 years before being decommissioned. One of the lesser understood aspects …
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Irradiation damage in neutron-irradiated Fe-Cr model alloys
Ferritic-martensitic (F-M) steels are considered as lead candidate structural materials for Generation IV fission reactors and future fusion reactors. Compared to austenitic stainless steels, these steels have superior properties in thermal conductivities and thermal expansion coefficients. In …
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First-principles studies on oxide nanoclusters in bcc Fe
… (ODS) steels also called Nanostructured Ferritic Alloys (NFA). NFA consist of Fe-Cr based ferritic/martensitic steels that contain highly dispersed nanometer-size Y-Ti-O nanoclusters, and are manufactured via powder metallurgy. The presence of nanoclusters leads to high temperature …
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Tensile behavior analysis on neutron irradiated Fe-Cr-C alloys using in-situ synchrotron X-ray and micromechanics modeling
Submission published under a 24 month embargo labeled 'Closed Access', the embargo will last until 2025-12-01