Transmission electron microscopy of ion irradiated ODS MA956 samples

Prabhakaran, Ramprashad; Lu, Yu; Wu, Yaqiao; Shao, Lin; Charit, Indrajit

doi:10.48806/2468645

Title: Transmission electron microscopy of ion irradiated ODS MA956 samples

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Abstract

Oxide dispersion strengthened (ODS) alloys are promising candidate materials for the next generation advanced nuclear reactors due to their superior irradiation resistance and mechanical properties. To better understand the effect of irradiation on MA956, it is essential to study higher dose (50-100 dpa) samples, so that the general trend of microstructural evolution and the resulting radiation-hardening can be deduced. Currently, ion irradiations are considered the only way to achieve doses beyond ~50 dpa in a practical time frame relevant to alloy and welding development programs. This dataset contains TEM characterization results of ODS MA956 samples that were ion irradiated under different conditions: Sample #5 (1.25 dpa at 190℃); Sample #9 (50 dpa at 190℃); Sample #15 (1.25dpa under 320℃); and Sample 17 (25 dpa at 320℃). TEM characterization focused on the irradiation induced defects (dislocation lines and loops) using the on-zone axis bright field STEM technique. These data were collected using a FEI Tecnai G2 F30 S/TEM at Microscopy and Characterization Suite (MaCS) at Center for Advanced Energy Studies (CAES), Idaho Falls, ID. This project (ion irradiation and TEM studies) was supported by the U.S. Department of Energy, Office of Nuclear Energy under DOE Idaho Operations Office Contract DE-AC07-05ID14517 asmore »« less

Authors:

; Lu, Yu;

; Shao, Lin; Charit, Indrajit

Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Boise State University
Boise State Univ., ID (United States)
Texas A&M University
University of Idaho

Publication Date:: Sun Apr 01 04:00:00 UTC 2018

Other Number(s):: transmission_electron_microscopy_of_ion_irradiated_ods_ma956_samples

DOE Contract Number:: AC07-05ID14517

Research Org.:: Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)

Sponsoring Org.:: USDOE Office of Nuclear Energy (NE)

OSTI Identifier:: 2468645

DOI:: https://doi.org/10.48806/2468645

Citation Formats


                    Prabhakaran, Ramprashad, Lu, Yu, Wu, Yaqiao, Shao, Lin, and Charit, Indrajit. Transmission electron microscopy of ion irradiated ODS MA956 samples.  United States: N. p., 2018. 
        Web.  doi:10.48806/2468645.

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                    Prabhakaran, Ramprashad, Lu, Yu, Wu, Yaqiao, Shao, Lin, & Charit, Indrajit. Transmission electron microscopy of ion irradiated ODS MA956 samples.  United States.  doi:https://doi.org/10.48806/2468645

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                    Prabhakaran, Ramprashad, Lu, Yu, Wu, Yaqiao, Shao, Lin, and Charit, Indrajit. 2018.  
"Transmission electron microscopy of ion irradiated ODS MA956 samples".  United States.  doi:https://doi.org/10.48806/2468645.  https://www.osti.gov/servlets/purl/2468645. Pub date:Sun Apr 01 04:00:00 UTC 2018

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@article{osti_2468645,

  title        = {Transmission electron microscopy of ion irradiated ODS MA956 samples},

  author       = {Prabhakaran, Ramprashad and Lu, Yu and Wu, Yaqiao and Shao, Lin and Charit, Indrajit},

  abstractNote = {Oxide dispersion strengthened (ODS) alloys are promising candidate materials for the next generation advanced nuclear reactors due to their superior irradiation resistance and mechanical properties. To better understand the effect of irradiation on MA956, it is essential to study higher dose (50-100 dpa) samples, so that the general trend of microstructural evolution and the resulting radiation-hardening can be deduced. Currently, ion irradiations are considered the only way to achieve doses beyond ~50 dpa in a practical time frame relevant to alloy and welding development programs. This dataset contains TEM characterization results of ODS MA956 samples that were ion irradiated under different conditions: Sample #5 (1.25 dpa at 190℃); Sample #9 (50 dpa at 190℃); Sample #15 (1.25dpa under 320℃); and Sample 17 (25 dpa at 320℃). TEM characterization focused on the irradiation induced defects (dislocation lines and loops) using the on-zone axis bright field STEM technique. These data were collected using a FEI Tecnai G2 F30 S/TEM at Microscopy and Characterization Suite (MaCS) at Center for Advanced Energy Studies (CAES), Idaho Falls, ID. This project (ion irradiation and TEM studies) was supported by the U.S. Department of Energy, Office of Nuclear Energy under DOE Idaho Operations Office Contract DE-AC07-05ID14517 as part of Nuclear Science User Facilities award #18-14784 (PI: Ramprashad Prabhakaran, PNNL).},

  doi          = {10.48806/2468645},

  journal      = {},

  number       = ,

  volume       = ,

  place        = {United States},

  year         = {Sun Apr 01 04:00:00 UTC 2018},

  month        = {Sun Apr 01 04:00:00 UTC 2018}

}

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DOI: https://doi.org/10.48806/2468645

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Oxide Dispersion Strengthened (ODS) alloys are considered as promising nuclear materials for the next generation advanced nuclear reactors due to their improved elevated temperature mechanical properties and radiation damage resistance. MA956 is a commercial ODS alloy with superior oxidation resistance and creep strength at elevated temperatures. The improved properties for ODS alloys can be attributed to the presence of dispersed nanosized oxide particles. These oxide particles can act as barriers to dislocation motion and provide additional sinks and sites for point defect recombination. Hence, their stability can greatly affect the properties of the irradiated ODS alloys. Besides, irradiation will inducemore »« less
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