TEM Characterization of Neutron Irradiated HfAl3-Al Composite Specimens
Particles comprised of a thermal neutron absorbing material (HfAl3) are dispersed in a metal matrix material with high thermal conductivity (aluminum) to conduct the heat generated by neutron capture away from the fuel and materials. This metal matrix composite is very promising for use as a conduction-cooled neutron absorber and has the potential to be useful as a shroud or heat sink for testing advanced fast reactor fuels and materials in an existing thermal reactor. To design and optimize the absorber block system for advanced reactor designs, fundamental understanding of the irradiation effect on material properties is necessary. This dataset contains TEM characterization results of neutron irradiated HfAl3-Al composite specimens. It is focused on the irradiation induced defects (dislocation lines and loops) characterization using the on-zone axis bright field STEM technique. This data was collected using a FEI Tecnai G2 F30 S/TEM at the Microscopy and Characterization Suite (MaCS), Center for Advanced Energy Studies (CAES).
Данни и ресурси
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Donna Guillen_RTE
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6 декември 2024, 18:49 (UTC+00:00) | |
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Images Used in MDPI Materials Article: Microstructure of Neutron Irradiated Al-Al3Hf Thermal Neutron Absorber Materials
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27 януари 2025, 22:29 (UTC+00:00) | |
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KGT 1404
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6 декември 2024, 18:48 (UTC+00:00) | |
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KGT 3595
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6 декември 2024, 18:48 (UTC+00:00) | |
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KGT 4102
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6 декември 2024, 19:08 (UTC+00:00) | |
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KGT 4104
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6 декември 2024, 19:11 (UTC+00:00) | |
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KGT 4105
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6 декември 2024, 19:15 (UTC+00:00) |
Допълнителна информация
Поле | Стойност |
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Автор | Donna Guillen, Yu Lu, Yaqiao Wu |
Last Updated | 27 януари 2025, 22:29 (UTC+00:00) |
Създаден | 21 ноември 2024, 22:47 (UTC+00:00) |
DOI Link | https://doi.org/10.48806/2478162 |
Instrument | FEI Tecnai G2 F30 STEM |
Statement of Credit | This work was performed by Battelle Energy Alliance, LLC under the DOE Idaho Operations Contract DE-AC07-05ID14517. Neutron irradiation in the ATR was conducted through DOE Office of Nuclear Energy, Nuclear Science User Facilities (NSUF) project BSU-15-8242. Post-irradiation examination was performed through NSUF Rapid Turnaround Experiment 21-4280. |