Before Nanomill

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).

ဒေတာနှင့် resource များ

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BFTEM_4105_49kx_A0B0_location 003.dm3

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BFTEM_4105_2.9kx_A0B0_lamella overview_007.tif

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BFTEM_4105_2.9kx_A0B0_lamella overview_007.png

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BFTEM_4105_25kx_A0B0_location 003.dm3

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BFTEM_4105_49kx_A0B0_location 001.tif

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BFTEM_4105_2.9kx_A0B0_lamella overview_002.dm3

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BFTEM_4105_2.9kx_A0B0_lamella overview_003.dm3

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BFTEM_4105_2.9kx_A0B0_lamella overview_008.tif

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BFTEM_4105_2.9kx_A0B0_lamella overview_008.png

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BFTEM_4105_2.9kx_A0B0_lamella overview_006.tif

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BFTEM_4105_2.9kx_A0B0_lamella overview_006.png

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BFTEM_4105_98kx_A0B0_location 001.tif

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BFTEM_4105_98kx_A0B0_location 001.png

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BFTEM_4105_25kx_A0B0_location 001.dm3

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BFTEM_4105_98kx_A0B0_location 002.tif

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BFTEM_4105_98kx_A0B0_location 002.png

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STEM and BFSTEM

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BFTEM_4105_75kx_A0B0_location 003.dm3

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BFTEM_4105_49kx_A0B0_location 001.dm3

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BFTEM_4105_2.9kx_A0B0_lamella overview_005.tif

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BFTEM_4105_2.9kx_A0B0_lamella overview_005.png

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BFTEM_4105_49kx_A0B0_location 002.dm3

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BFTEM_4105_2.9kx_A0B0_lamella overview_004.dm3

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EDS

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BFTEM_4105_75kx_A0B0_location 003.tif

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BFTEM_4105_75kx_A0B0_location 003.png

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BFTEM_4105_25kx_A0B0_location 002.tif

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BFTEM_4105_25kx_A0B0_location 002.png

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BFTEM_4105_2.9kx_A0B0_lamella overview_007.dm3

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BFTEM_4105_98kx_A0B0_location 002.dm3

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BFTEM_4105_15kx_A0B0_location 002.dm3

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BFTEM_4105_25kx_A0B0_location 001.tif

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BFTEM_4105_25kx_A0B0_location 001.png

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BFTEM_4105_15kx_A0B0_location 001.tif

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BFTEM_4105_15kx_A0B0_location 001.png

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BFTEM_4105_2.9kx_A0B0_lamella overview_006.dm3

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BFTEM_4105_15kx_A0B0_location 001.dm3

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BFTEM_4105_49kx_A0B0_location 003.tif

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BFTEM_4105_49kx_A0B0_location 003.png

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BFTEM_4105_15kx_A0B0_location 003.tif

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BFTEM_4105_15kx_A0B0_location 003.png

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BFTEM_4105_49kx_A0B0_location 002.tif

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BFTEM_4105_49kx_A0B0_location 002.png

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BFTEM_4105_2.9kx_A0B0_lamella overview_008.dm3

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BFTEM_4105_25kx_A0B0_location 002.dm3

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BFTEM_4105_2.9kx_A0B0_lamella overview_001.dm3

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BFTEM_4105_2.9kx_A0B0_lamella overview_003.tif

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BFTEM_4105_2.9kx_A0B0_lamella overview_003.png

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BFTEM_4105_15kx_A0B0_location 002.tif

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BFTEM_4105_15kx_A0B0_location 002.png

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BFTEM_4105_2.9kx_A0B0_lamella overview_002.tif

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BFTEM_4105_2.9kx_A0B0_lamella overview_002.png

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BFTEM_4105_2.9kx_A0B0_lamella overview_001.tif

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BFTEM_4105_2.9kx_A0B0_lamella overview_001.png

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BFTEM_4105_2.9kx_A0B0_lamella overview_005.dm3

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BFTEM_4105_98kx_A0B0_location 001.dm3

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BFTEM_4105_15kx_A0B0_location 003.dm3

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BFTEM_4105_25kx_A0B0_location 003.tif

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BFTEM_4105_25kx_A0B0_location 003.png

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BFTEM_4105_2.9kx_A0B0_lamella overview_004.tif

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BFTEM_4105_2.9kx_A0B0_lamella overview_004.png

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နောက်ဆက်တွဲ သတင်းအချက်အလက်များ

Field တန်ဖိုး
ရေးသားသူ Donna Guillen, Yu Lu, Yaqiao Wu
နောက်ဆုံး ပြင်ဆင်ခဲ့သော အချိန် ဒီဇင်ဘာ 6, 2024, 19:20 (UTC)
ဖန်တီးခဲ့သော အချိန် ဒီဇင်ဘာ 6, 2024, 19:20 (UTC)
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.