| About this Abstract |
| Meeting |
2020 TMS Annual Meeting & Exhibition
|
| Symposium
|
Accelerated Materials Evaluation for Nuclear Applications Utilizing Irradiation and Integrated Modeling
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| Presentation Title |
Development of Advanced Low N-12Cr (wt.%) Ferritic/Martensitic Steel for Reactor Applications |
| Author(s) |
Connor J. Rietema, Tarik A. Saleh, Benjamin Eftink, Stuart A. Maloy, Osman Anderoglu, Md Mehadi Hassan, Amy J. Clarke, Kester D. Clarke |
| On-Site Speaker (Planned) |
Connor J. Rietema |
| Abstract Scope |
Low nitrogen (<10 wppm) vacuum-induction melted (VIM) lab heats of the ferritic/martensitic alloy HT-9 have shown significant resistance to ductility loss after low temperature (<0.3 Tm) irradiation. Here we examine the role of interstitial nitrogen on the effect of ductility loss after low temperature irradiation. Interstitial nitrogen levels are controlled by strategic titanium or zirconium microalloy additions. High nitrogen (440 wppm) and low nitrogen (10 wppm) VIM heats, along with four heats containing various levels of titanium and one zirconium-containing heat, have been produced. Following initial characterization of the interstitial nitrogen levels in each alloy utilizing time-of-flight secondary ion mass spectrometry (TOF-SIMS) and internal friction measurements, proton irradiation at 300 ˚C to low dpa and subsequent characterization of the irradiated microstructures and properties was performed. |
| Proceedings Inclusion? |
Undecided |