About this Abstract |
Meeting |
2022 TMS Annual Meeting & Exhibition
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Symposium
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Seeing is Believing -- Understanding Environmental Degradation and Mechanical Response Using Advanced Characterization Techniques: An SMD Symposium in Honor of Ian M. Robertson
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Presentation Title |
On the Evolution of Dislocation Structures in Irradiated Ferritic-Martensitic Steels |
Author(s) |
G. Robert Odette, Ben Eftink, Jack Haley, David Sprouster |
On-Site Speaker (Planned) |
G. Robert Odette |
Abstract Scope |
Unlike the case of fcc austenitic steels, network dislocation evolution has not been well characterized and modeled in irradiated bcc ferritic martensitic steels. This knowledge gap is very significant, since the evolution of loops and pre-existing dislocation structures affect point defect sink strengths and their biases, as well as the irradiated alloy constitutive properties. TEM shows initially straight screw dislocations evolve into helical configurations, in a simple Fe-Cr binary alloy, due to vacancy bias driven climb. Similar behavior is observed in more complex steels, along with increases in both loop and network dislocation densities. APT studies show dislocations are sites for strong solute segregation and precipitation, including non-equilibrium phases. This talk is divided into three parts: a) an overview the critical need for comprehensive experimental dislocation characterization; b) results from TEM studies; and, c) results from XRD studies, including data from the literature. |
Proceedings Inclusion? |
Planned: |
Keywords |
Nuclear Materials, Mechanical Properties, Other |