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Materials Science

D-Index
46
Citations
7010
World Ranking
11512
National Ranking
2693

Overview

Thak Sang Byun is affiliated with Oak Ridge National Laboratory in the United States. Their research primarily focuses on the fields of Engineering and Materials Science, with substantial contributions in Mechanical Engineering, Materials Chemistry, Metals and Alloys, Mechanics of Materials, and Automotive Engineering.

The principal research topics of Byun encompass Additive Manufacturing Materials and Processes, Fusion materials and technologies, Nuclear Materials and Properties, Hydrogen embrittlement and corrosion behaviors in metals, Microstructure and Mechanical Properties of Steels, High Entropy Alloys Studies, and Advanced materials and composites.

Byun has published extensively, with key papers including:

  • Mechanical behavior of additively manufactured and wrought 316L stainless steels before and after neutron irradiation, 2021, Journal of Nuclear Materials
  • Creep behavior of 316 L stainless steel manufactured by laser powder bed fusion, 2021, Journal of Nuclear Materials
  • Precipitation-site competition in duplex stainless steels: Cu clusters vs spinodal decomposition interfaces as nucleation sites during thermal aging, 2020, Acta Materialia
  • Degradation of impact toughness in cast stainless steels during long-term thermal aging, 2020, Journal of Nuclear Materials
  • Irradiation hardening and ductility loss of Eurofer97 steel variants after neutron irradiation to ITER-TBM relevant conditions, 2021, Fusion Engineering and Design

Their frequent co-authors include:

  • Timothy G. Lach
  • Maxim N. Gussev
  • Kurt A. Terrani
  • Annabelle Le Coq
  • Kory Linton

Byun often publishes in specialized venues. The most frequent publication venues are:

  • Journal of Nuclear Materials
  • SSRN Electronic Journal
  • Transactions of the American Nuclear Society - Volume 123
  • Acta Materialia
  • JOM

Best Publications

  • Handbook of SiC properties for fuel performance modeling

    Lance L. Snead;Takashi Nozawa;Yutai Katoh;Thak Sang Byun

  • On the stress dependence of partial dislocation separation and deformation microstructure in austenitic stainless steels

    T.S. Byun

  • Temperature dependence of strain hardening and plastic instability behaviors in austenitic stainless steels

    T.S Byun;N Hashimoto;K Farrell

  • Deformation mode maps for tensile deformation of neutron-irradiated structural alloys

    K. Farrell;T.S. Byun;N. Hashimoto

  • Tensile properties and inhomogeneous deformation of ferrite-martensite dual-phase steels

    Thak Sang Byun;In Sup Kim

  • Plastic instability in polycrystalline metals after low temperature irradiation

    T.S. Byun;K. Farrell

  • Helium and hydrogen induced hardening in 316LN stainless steel

    J.D Hunn;E.H Lee;T.S Byun;L.K Mansur

  • Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part II—Mechanistic models and predictions

    Jeoung Han Kim;Thak Sang Byun;David T. Hoelzer;Chan Hee Park

  • Local mechanical properties of Alloy 82/182 dissimilar weld joint between SA508 Gr.1a and F316 SS at RT and 320 °C

    Jin Weon Kim;Kyoungsoo Lee;Jong Sung Kim;Thak Sang Byun

  • On the origin of deformation microstructures in austenitic stainless steel: part I—microstructures

    E.H. Lee;T.S. Byun;J.D. Hunn;M.H. Yoo

  • Plastic deformation in 316LN stainless steel – characterization of deformation microstructures

    T.S Byun;E.H Lee;J.D Hunn

  • Dose dependence of defect accumulation in neutron irradiated copper and iron

    M. Eldrup;B.N. Singh;S.J. Zinkle;T.S. Byun

  • Irradiation hardening behavior of polycrystalline metals after low temperature irradiation

    T.S Byun;K Farrell

  • On the origin of deformation microstructures in austenitic stainless steel: Part II—Mechanisms

    E.H Lee;M.H Yoo;T.S Byun;J.D Hunn

  • Stability of MX-type strengthening nanoprecipitates in ferritic steels under thermal aging, stress and ion irradiation

    L. Tan;T.S. Byun;Y. Katoh;L.L. Snead

  • Deformation mode map of irradiated 316 stainless steel in true stress–dose space

    T.S. Byun;N. Hashimoto;K. Farrell

  • A theoretical model for determination of fracture toughness of reactor pressure vessel steels in the transition region from automated ball indentation test

    Thak Sang Byun;Jin Weon Kim;Jun Hwa Hong

  • Measurement of through-the-thickness variations of mechanical properties in SA508 Gr.3 pressure vessel steels using ball indentation test technique

    T.S. Byun;J.H. Hong;F.M. Haggag;K. Farrell

  • Temperature effect on the low-cycle fatigue behavior of type 316L stainless steel: Cyclic non-stabilization and an invariable fatigue parameter

    Seong-Gu Hong;Seong-Gu Hong;Soon-Bok Lee;Thak-Sang Byun

  • Temperature dependence of strengthening mechanisms in the nanostructured ferritic alloy 14YWT: Part I—Mechanical and microstructural observations

    Jeoung Han Kim;Thak Sang Byun;David T. Hoelzer;Seong-Woong Kim

  • Tensile properties of Inconel 718 after low temperature neutron irradiation

    T.S. Byun;K. Farrell

  • Application of intercritical heat treatment to improve toughness of SA508 Cl.3 reactor pressure vessel steel

    Yeon-Sang Ahn;Hong-Deok Kim;Thak-Sang Byun;Yong-Jun Oh

  • Ion-irradiation-induced hardening in Inconel 718

    J.D Hunn;E.H Lee;T.S Byun;L.K Mansur

Frequent Co-Authors

Stuart A. Maloy
Stuart A. Maloy Pacific Northwest National Laboratory
David T. Hoelzer
David T. Hoelzer Oak Ridge National Laboratory
Yutai Katoh
Yutai Katoh Oak Ridge National Laboratory
Steven J. Zinkle
Steven J. Zinkle University of Tennessee at Knoxville
Hsin Wang
Hsin Wang Oak Ridge National Laboratory
Yukinori Yamamoto
Yukinori Yamamoto Oak Ridge National Laboratory
Ryan R. Dehoff
Ryan R. Dehoff Oak Ridge National Laboratory
Peter Hosemann
Peter Hosemann University of California, Berkeley
Lizhen Tan
Lizhen Tan Oak Ridge National Laboratory

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