NSUF 16-804: Investigation of Deformation Mechanisms of an Intermetallic-strengthened Alloy with and without Heavy Ion Irradiation
A series of Zr-containing ferritic alloys were recently developed with the aid of computational thermodynamics in an effort to develop advanced structural materials for future nuclear reactors. Samples with acceptable performance from tensile, creep, and thermal-aging-resistance tests were selected to undergo radiation-tolerance tests. The radiation response of the alloys was studied using Fe+2 ion irradiations up to a nominal dose of 50 dpa at the University of Wisconsin. Post-irradiation microstructural characterization showed defect cluster formations and amorphization of Fe2Zr-type Laves phase. The corresponding mechanical property changes will be studied using nanoindentation. Transmission electron microscopy studies will be carried out to understand the indentation deformation mechanisms of the irradiated material. This study provides first-hand data on radiation tolerance of Laves phase strengthened alloys, as well as an enhanced fundamental understanding of interphase-defect interactions, radiation-hardening, and deformation mechanisms of materials with complex structures.
Additional Info
| Field | Value |
|---|---|
| Awarded Institution | University of Wisconsin |
| Embargo End Date | 2026-02-27 |
| Facility Tech Lead | Kory Linton |
| NSUF Call | FY 2017 RTE 1st Call |
| PI | Kumar Sridharan |
| Project Member | Dr. Lizhen Tan, Research Staff - Oak Ridge National Laboratory (https://orcid.org/0000-0002-3418-2450) |
| Project Member | Dr. Tianyi Chen, Assistant Professor - Oregon State University (https://orcid.org/0000-0003-2880-824X) |
| Project Notes | Awarded on 12/16/2016 |
| Project Type | RTE |
| Publication | Effect of carbon ion irradiation on Ag diffusion in SiC Tyler Gerczak, bin leng, Kumar Sridharan, Izabela Szlufarska Journal of Nuclear Materials 471 2017-04-17 http://www.sciencedirect.com/science/article/pii/S0022311515303251#ack0010 |
| RTE Number | 804 |