Global ETD Search
Search theses and dissertations gathered from participating repositories worldwide. Every result links back to the library that holds it. No account is needed.
Results
Showing 1 to 5 of 5 for “"Ferritic martensitic steel"”.
-
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 …
-
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 …
-
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 …
-
Radiation-induced microstructural and mechanical property modifications in advanced alloys
… alloys, including Fe–20Cr–25Ni–Nb 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, …
-
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 …