NSUF 16-832: Ion beam radiation damage assessment in advanced Ferritic/Martensitic (F/M) alloys
In-situ transmission electron microscopy (TEM) combined with ion irradiation is a powerful tool to characterize the microstructural evolution under irradiation because the microstructure evolution can be followed as the damage proceeds. The objective of the work is to investigate the microstructure evolution under ion irradiation in advanced Ferritic/Martensitic alloys (Fe-9Cr F/M steel T91 and Fe-12Cr F/M steel HT9, ODS steel 14YWT, and model alloys Fe-9Cr and Fe-12Cr).
The samples will be irradiated with 1 MeV Kr++ ions at an incident angle ~15º from the specimen normal. The ion flux to be used is 6.2 × 1011 ions/cm2/s which correspond to about 1.12 × 10-3 dpa/s based on SRIM simulations. The focus of the experiments will be to look at the dislocation loops induced by irradiation and characterize their burgers vectors as well at their type (intersititial vs. vacancy) and density as a function of dose since the irradiations are done IN-SITU. Such in-situ experiments are invaluable to obtain kinetics of the defect formation in these alloys and show how the irradiation induced damage spatially correlates with the pre-existing microstructure. It is also a necessary method in order to understand how the microstructures observed in ion (and neutron) irradiated bulk samples (examined ex-situ) develop because, in these cases, only snapshots are available at limited doses. As far as bigger impact, these experiments are part of a larger effort involving several universities with the goal to demonstrate the capability of predicting the evolution of microstructure of F/M alloys in-reactor and at high doses, using ion irradiation as a surrogate for reactor irradiations.
Note that the samples will be prepared by FIB lift out at NCSU, and although chemical analysis is not possible during the experiments at the IVEM (since there is no energy filter on the microscope), post irradiation chemical analysis will be done at NCSU using chemi-STEM method.
The period of performance should be between January 2017 and August 30th 2017
Información adicional
| Campo | Valor |
|---|---|
| Awarded Institution | North Carolina State University |
| Embargo End Date | 2026-04-23 |
| Facility Tech Lead | Wei-Ying Chen |
| NSUF Call | FY 2017 RTE 1st Call |
| PI | Djamel Kaoumi |
| Project Member | Professor Djamel Kaoumi, Professor - North Carolina State University (https://orcid.org/0000-0001-7055-0444) |
| Project Member | Dr. Ce Zheng, Postdoctoral researcher - North Carolina State University (https://orcid.org/0000-0001-8509-9385) |
| Project Notes | Awarded on 12/16/2016 |
| Project Type | RTE |
| Publication | Effect of dose on irradiation-induced loop density and Burgers vector in ion-irradiated ferritic/ martensitic steel HT9 Ce Zheng, Stuart Maloy, Djamel Kaoumi Philosophical Magazine 98 2018-07-04 https://www.tandfonline.com/doi/full/10.1080/14786435.2018.1490825 |
| Publication | Combined use of in-situ and ex-situ TEM to characterize ion irradiation induced dislocation loops in F/M steels Djamel Kaoumi, Ce Zheng E-MRS 2018 2018-06-18 - 2018-06-22 |
| Publication | Dose effect on the irradiation induced loop density and Burgers vector in ion-irradiated ferritic/martensitic steel HT9 through in-situ TEM, Djamel Kaoumi, Ce Zheng MMM 2018 2018-10-28 - 2018-11-02 |
| Publication | Dose effect on the irradiation induced loop density & Burgers vector in ion-irradiated alloy T91 irradiated in-situ in a TEM Djamel Kaoumi, Ce Zheng TMS 2018 2018-03-11 - 2018-03-15 |
| Publication | Ion irradiation effects on commercial PH 13-8 Mo maraging steel Corrax Ce Zheng, Ryan Schoell, Peter Hosemann, Djamel Kaoumi Journal of Nuclear Materials 514 2019-02-01 https://www.sciencedirect.com/science/article/pii/S0022311518312819 |
| Publication | Use of In-Situ TEM to study the Dose Effect on the Irradiation Induced Loop Density and Burgers Vector in an Ion-Irradiated F/M Steel for Nuclear Applications Djamel Kaoumi, Ce Zheng WOTWISI-5 2018-04-11 - 2018-04-13 |
| Publication | Radiation induced segregation and precipitation behavior in self-ion irradiated Ferritic/Martensitic HT9 steel Maria A Auger, Djamel Kaoumi, Ce Zheng Journal of Nuclear Materials 491 2017-09-01 http://www.sciencedirect.com/science/article/pii/S0022311517301733#ack0010 |
| RTE Number | 832 |