NSUF 24-4797: An evaluation of effects of ion irradiation on crystal, mechanical, and microstructural properties of Alloy 709

Advanced manufacturing of structural materials such as Alloy 709 for Gen IV nuclear reactors has been evaluated. Even though materials, which have been fabricated using conventional methods, behavior under reactor environments has been studied and reported at great extent, radiation effects on materials fabricated using advanced techniques such as friction consolidation and also recently developed materials need to be studied. To support that effort, we propose to study high-temperature ion irradiation behavior of alloy 709 in this proposal. Under this work, 4 samples from each of A709 that are fabricated using conventional forging techniques and friction consolidation will be used. These 4 samples from each material will be irradiated to attain dose values of 100, 200, 300, and 400 dpa using 3.5 MeV Fe2+ at Texas A&M Ion Beam Lab at a peak swelling temperature of 575 °C. These samples will be characterized using X-ray diffraction and electron microscopic techniques to understand the radiation effects on A709’s crystal structure and microstructure. Mechanical properties of the samples will be characterized using hardness corresponding to nano-indentation. These different properties will also be compared to identify any correlation between each property.

Dodatne informacije

Polje	Vrednost
Award Announced Date	2024-02-02T12:08:47.143
Awarded Institution	Pacific Northwest National Laboratory
Facility Tech Lead	Lin Shao, Stuart Maloy
Irradiation Facility	Accelerator Laboratory
PI	Chinthaka Silva
PI Email	[email protected]
Project Type	RTE
RTE Number	None