Lizhen Tan

Employment

• Oak Ridge National Laboratory
  2009 - Present

Education

• University of Wisconsin Madison Ph.D.
  2000 - 2003

Projects & Funding

Projects & funding information is unavailable.

Publications (126)

• Creep behavior of an additively manufactured 9Cr steel in the as-built condition
  Journal of Nuclear Materials 2022 DOI: 10.1016/j.jnucmat.2022.153943
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• Long-Term Thermal Aging Effect Evaluation for Grade 92 and 316L at The LWR Relevant Temperature
  2021 DOI: 10.2172/1843699
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• Microstructure and mechanical properties of high Mn-containing ferritic-martensitic alloys exposed to cyclical thermal treatment
  Materials Science and Engineering: A 2021 DOI: 10.1016/j.msea.2021.141143
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• Segregation behavior and phase instability of Eurofer97 after neutron irradiation to 72 dpa
  Journal of Nuclear Materials 2021 DOI: 10.1016/j.jnucmat.2021.152834
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• Effects of helium on irradiation response of reduced-activation ferritic-martensitic steels: Using nickel isotopes to simulate fusion neutron response
  Journal of Nuclear Materials 2021 DOI: 10.1016/j.jnucmat.2020.152634
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• Microstructures and mechanical properties of a modified 9Cr ferritic-martensitic steel in the as-built condition after additive manufacturing
  Journal of Nuclear Materials 2021 DOI: 10.1016/j.jnucmat.2020.152742
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• Advanced synchrotron characterization techniques for fusion materials science
  Journal of Nuclear Materials 2021 DOI: 10.1016/j.jnucmat.2020.152574
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• ORNL Post-irradiation Examination (LAMDA) Final Report on Characterization of Irradiated Grade 92 Ferritic-Martensitic Steels
  2020 DOI: 10.2172/1765483
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• Intermediate-Term Thermal Aging Effect Evaluation for Grade 92 and 316L at The LWR Relevant Temperature
  2020 DOI: 10.2172/1761620
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• The correlation between microstructure and nanoindentation property of neutron-irradiated austenitic alloy D9
  Acta Materialia 2020 DOI: 10.1016/j.actamat.2020.05.020
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• Microstructural stability of tantalum-alloyed ferritic-martensitic steel with neutron irradiation to 7.4 dpa at ~490 °C
  Materialia 2020 DOI: 10.1016/j.mtla.2020.100608
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• Report on partially complete post-irradiation-examination of the INL samples
  2020 DOI: 10.2172/1651352
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• Second Annual Progress Report on Correlation Between Microstructure and Mechanical Properties of Neutron-Irradiated Ferritic-Martensitic and Austenitic Steels
  2020 DOI: 10.2172/1651349
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• Contrasting roles of Laves_Cr<inf>2</inf>Nb precipitates on the creep properties of novel CuCrNbZr alloys
  Materials Science and Engineering A 2020 DOI: 10.1016/j.msea.2020.139110
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• Coupling computational thermodynamics with density-function-theory based calculations to design L1<inf>2</inf> precipitates in Fe[sbnd]Ni based alloys
  Materials and Design 2020 DOI: 10.1016/j.matdes.2020.108592
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• Post-Irradiation-Examination of the ORNL and LANL Samples
  2019 DOI: 10.2172/1651367
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• NSUF Tensile Testing and Characterization of Irradiated Grade 92 Ferritic-Martensitic Steels
  2019 DOI: 10.2172/1524855
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• Deuterium retention in advanced steels for fusion reactor structural application
  Journal of Nuclear Materials 2019 DOI: 10.1016/j.jnucmat.2019.01.020
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• Interactions between displacement cascade and dislocation and their influences on Peierls stress in Fe-20Cr-25Ni alloys
  Computational Materials Science 2019 DOI: 10.1016/j.commatsci.2018.12.018
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• Development of nanoprecipitates-strengthened advanced ferritic alloys for nuclear reactor applications
  2019 DOI: 10.2172/1526385
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