Neutron irradiation induced defects and clustering in NF616 and T91
Abstract
NF616 is a third-generation ferritic martensitic steel, developed to have better creep resistance than the prior generation T91. Unlike relatively numerous studies of T91, there is a lack of understanding of the irradiation effect on the microstructural evolution and mechanical response of NF616. This work evaluated the microstructures and radiation hardening of NF616 irradiated up to 8.2 displacement per atom (dpa) at 292 °C – 431 °C, compared with T91 from two heats. Dislocation loops were observed in all investigated samples. NF616 exhibited comparable loop size but slightly lower loop density than those in the general T91 heat at 430 °C. Cavities were only observed in NF616 at 431 °C but absent at lower irradiation temperatures (292 °C and 359 °C). Ni-rich clusters were also observed in NF616 at 431 °C, while only weak Ni-clustering were observed at lower irradiation temperatures. Compared to the general T91 heat, NF616 demonstrated better swelling resistance (e.g., one third of swelling in the general T91 heat at 430 °C), a slightly higher number density of Ni-rich clusters, and slightly lower radiation hardening. The low-carbon T91 showed the greatest hardening with the largest swelling and loop sizes, despite its lowest irradiation temperature and intermediate dose.more »
- Authors:
-
[1];
[1]
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Materials Science and Technology Division
- Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
- Publication Date:
- Research Org.:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Org.:
- USDOE Office of Nuclear Energy (NE)
- OSTI Identifier:
- 1814354
- Alternate Identifier(s):
- OSTI ID: 1815103
- Grant/Contract Number:
- AC05-00OR22725
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Journal of Nuclear Materials
- Additional Journal Information:
- Journal Volume: 552; Journal Issue: 1; Journal ID: ISSN 0022-3115
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; Microstructure; Dislocation loops; Cavities; Hardening
Citation Formats
Zhong, Weicheng, Saleh, Tarik A., and Tan, Lizhen. Neutron irradiation induced defects and clustering in NF616 and T91. United States: N. p., 2021.
Web. doi:10.1016/j.jnucmat.2021.153001.
Zhong, Weicheng, Saleh, Tarik A., & Tan, Lizhen. Neutron irradiation induced defects and clustering in NF616 and T91. United States. https://doi.org/10.1016/j.jnucmat.2021.153001
Zhong, Weicheng, Saleh, Tarik A., and Tan, Lizhen. Fri .
"Neutron irradiation induced defects and clustering in NF616 and T91". United States. https://doi.org/10.1016/j.jnucmat.2021.153001. https://www.osti.gov/servlets/purl/1814354.
@article{osti_1814354,
title = {Neutron irradiation induced defects and clustering in NF616 and T91},
author = {Zhong, Weicheng and Saleh, Tarik A. and Tan, Lizhen},
abstractNote = {NF616 is a third-generation ferritic martensitic steel, developed to have better creep resistance than the prior generation T91. Unlike relatively numerous studies of T91, there is a lack of understanding of the irradiation effect on the microstructural evolution and mechanical response of NF616. This work evaluated the microstructures and radiation hardening of NF616 irradiated up to 8.2 displacement per atom (dpa) at 292 °C – 431 °C, compared with T91 from two heats. Dislocation loops were observed in all investigated samples. NF616 exhibited comparable loop size but slightly lower loop density than those in the general T91 heat at 430 °C. Cavities were only observed in NF616 at 431 °C but absent at lower irradiation temperatures (292 °C and 359 °C). Ni-rich clusters were also observed in NF616 at 431 °C, while only weak Ni-clustering were observed at lower irradiation temperatures. Compared to the general T91 heat, NF616 demonstrated better swelling resistance (e.g., one third of swelling in the general T91 heat at 430 °C), a slightly higher number density of Ni-rich clusters, and slightly lower radiation hardening. The low-carbon T91 showed the greatest hardening with the largest swelling and loop sizes, despite its lowest irradiation temperature and intermediate dose. The calculated hardening from loops, cavities and Ni-rich clusters using the classic dispersed barrier-hardening model had reasonable agreement with the experiment-derived results, with the primary hardening contribution attributed to dislocation loops.},
doi = {10.1016/j.jnucmat.2021.153001},
journal = {Journal of Nuclear Materials},
number = 1,
volume = 552,
place = {United States},
year = {Fri Apr 09 00:00:00 EDT 2021},
month = {Fri Apr 09 00:00:00 EDT 2021}
}
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