Small Scale Creep Testing of 14YWT via In-situ Transmission Electron Microscopy Irradiation and Nanoindentation
- Idaho National Laboratory (INL), Idaho Falls, ID (United States); Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
- Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)
- Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); University of Tennessee, Knoxville, TN (United States)
- Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
- Los Alamos National Laboratory (LANL), Los Alamos, NM (United States); Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)
The next generation of nuclear materials must withstand harsh operating conditions such as high temperatures and irradiation doses. Nanostructured ferritic alloys like oxide dispersion strengthened steels, especially 14YWT, have shown promise as a structural material to withstand these harsh operating conditions. For application, understanding the irradiation enhanced creep of the structural components is fundamental to evaluating the service life in a reactor. Challenges with evaluating irradiation enhanced creep are related to the limited space in nuclear reactors and the expense of conducting post irradiation experiments on irradiated cladding. Ion irradiations are considered to expedite irradiation testing, but such experiments have restricted depth of penetration into the material, limiting the ability to characterize changes to material properties after irradiation. Small scale mechanical testing can be used with ion beam irradiations as a potential avenue to evaluate the irradiation enhanced creep of materials. In this study, in-situ transmission electron microscopy nanopillar creep studies on 14YWT were performed and simultaneously ion beam irradiated with 2.8 MeV Au4+ ions. It was observed that the ion beam irradiation did increase the measured strain rate of the materials. In addition, ex-situ nanoindentation creep studies were performed over a range of temperatures on control 14YWT, and it was observed that there was a change in the deformation mechanism between 873 K and 1073 K that agrees well with macro-scale mechanical testing. Furthermore, these results show promise for applying these techniques to nuclear materials in the future.
- Research Organization:
- Idaho National Laboratory (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA); USDOE Laboratory Directed Research and Development (LDRD) Program
- Grant/Contract Number:
- AC07-05ID14517; NA0003525
- OSTI ID:
- 1999205
- Report Number(s):
- INL/JOU-22-66958-Rev000; TRN: US2405437
- Journal Information:
- JOM. Journal of the Minerals, Metals & Materials Society, Vol. 75, Issue 7; ISSN 1047-4838
- Publisher:
- SpringerCopyright Statement
- Country of Publication:
- United States
- Language:
- English
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