NSUF 24-4880: The effect of radiation temperature on H/He core-shell structures in nuclear structural materials
The objective of this project is to investigate (1) the ability of nuclear materials to trap, transport, and release transmutation and decay gases, (2) to understand the hydrogen/noble gas interaction within irradiation-induced nano-cavities, and (3) to assess trapped gas impact on degradation of mechanical properties in nuclear structural materials. There is a critical need to understand the mechanisms for gas trapping, mobility, and release in irradiated materials. We propose this work to grow the scientific understanding for hydrogen/ helium/ matrix interactions to develop methods for improving the lifetime, safety, and stability of nuclear reactor components, fuels, and waste forms. We hypothesize that (1) irradiation below the vacancy mobility temperature of the target material results in the formation of a high density of H-stabilizing He-filled nanocavities that serve as sinks for radiation defects at higher irradiation temperatures; and (2) mechanical behavior may be positively influenced by the presence of the high density of gas-filled nanocavities due to a change in deformation mechanism. We take the approach of a combined multi-beam ion-irradiation and post-irradiation examination campaign. Triple-ion beam irradiation using helium in conjunction with hydrogen and target self-ions will be conducted on Ni targets at temperatures at or below the vacancy mobility onset temperature of the target and again at elevated temperatures. Post-irradiation examination will focus primarily on analytical STEM characterization and nanomechanical testing. This project leverages unique and advanced NSUF capabilities including triple-beam ion irradiation and extensive post-irradiation examination capabilities available only at the participating institutions. The scientific outcome of this project will be a fundamental understanding of hydrogen and helium behavior within a radiation environment relative to radiation temperature. By understanding transmutation gas behavior and determining their potential benefits, this proposed work will facilitate the broader engineering impact of helping to design fuels, structural alloys, and waste forms with safety impacts and risks in mind. This project is relevant to DOE-NE because one of the greatest hurdles facing current, and particularly advanced reactor concepts, is understanding transmutation gas, fission gas, and decay gas interactions, transport, and release and how to mitigate the material degradation that results to prolong the safe operation lifetime of reactors. This project seeks to provide foundational understanding of gas-matrix interaction behavior during irradiation that could fill this critical technological gap.
추가 정보
| 필드 | 값 |
|---|---|
| Award Announced Date | 2024-02-02T12:35:02.26 |
| Awarded Institution | Oak Ridge National Laboratory |
| Facility Tech Lead | Kevin Field |
| Irradiation Facility | Michigan Ion Beam Laboratory |
| PI | Maxim Gussev |
| PI Email | [email protected] |
| Project Type | RTE |
| RTE Number | None |