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Nuclear Science User Facilities 108 Microstructural and Mechanical Characterization of Self-Ion Irradiated Grade 92 Steel Indrajit Charit University of Idaho icharituidaho.edu Ferritic-martensitic F-M steels have the potential to be employed in advanced reactors. One of these Grade 92 9Cr-2W steel is being considered for structural applications in advanced nuclear energy systems. It has good mechan- ical and thermophysical properties and is considered to have potential for both in-core and out-of-core applica- tions. Still the irradiation performance of this alloy is not fully understood because of limited available data. This experiment could lead to a better understanding of Grade 92s irradia- tion performance in fuel cladding and structural materials for advanced reactors. If proven successful high- performance materials such as Grade 92 steel would help improve the safety and reliability of future reactors and give them a longer service life. Project Description In this project Grade 92 samples were irradiated with high energy Fe2 ions at theTexas AM University Ion Beam Laboratory and the induced micro- structural evolution and mechanical properties that resulted were inves- tigated. Irradiated specimens were prepared for transmission electron microscopy TEM using a focused ion beam FIB. Microstructural char- acterization of the irradiated speci- mens was performed usingTEM and mechanical properties were evaluated using the nanoindentation technique. Accomplishments Grade 92 steel specimens were irradi- ated to 10 50 and 100 displacements per atom dpa using the IoneX 1.7 MVTandetron accelerator.This effort was coordinated by Professor Lin Shao and graduate student Lloyd Price. This experiment could lead to a better understanding of Grade 92s irradiation performance in fuel cladding and structural materials for advanced reactors. Figure 1. The calculated irradiation damage profile in terms of dpa versus length.