Thak Sang Byun
Pacific Northwest National Laboratory
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Publication
Featured researches published by Thak Sang Byun.
Environmental Degradation of Materials in Nuclear Power Systems | 2017
Thak Sang Byun; Timothy G. Lach; Ying Yang; Changheui Jang
Thermal degradation of cast stainless steels was studied to provide an extensive knowledgebase for the assessment of structural integrity during extended operations of reactor coolant systems. The CF3 and CF8 series cast stainless steels with relatively low (5–12%) δ-ferrite contents were thermally aged at 290–400 °C for up to 10,000 h and tested to measure changes in tensile and impact properties. The aging treatments caused significant reduction of tensile ductility, but only slight softening or negligible strength change. The thermal aging also caused significant reduction of upper shelf energy and large shift of ductile-brittle transition temperature (ΔDBTT). The most influential factor in thermal degradation was ferrite content because of the major degradation mechanism occurring in the phase, while the nitrogen and carbon contents caused only weak effects. An integrated model is being developed to correlate the mechanical property changes with microstructural and compositional parameters.
Environmental Degradation of Materials in Nuclear Power Systems | 2017
Timothy G. Lach; Thak Sang Byun
Thermal aging degradation of cast austenitic stainless steels (CASS) was studied by electron microscopy to understand the mechanisms for thermal embrittlement potentially experienced during extended operations of light water reactor coolant systems. Four CASS alloys—CF3, CF3M, CF8, and CF8M—were thermally aged up 1500 h at 330 and 400 °C, and the microstructural evolution of the material was characterized by analytical aberration-corrected scanning transmission electron microscopy. The primary microstructural and compositional changes during thermal aging were spinodal decomposition of the δ-ferrite into α/α′, precipitation of G-phase in the δ-ferrite, segregation of solute to the austenite/ferrite interphase boundary, and growth of M23C6 carbides on the austenite/ferrite interphase boundary. These changes were shown to be highly dependent on aging temperature and chemical composition, particularly the amount of C and Mo. A comprehensive model is being developed to correlate the microstructural evolution with mechanical behavior and simulation.
Journal of Nuclear Materials | 2016
David T. Hoelzer; Kinga A. Unocic; Mikhail A. Sokolov; Thak Sang Byun
Journal of Alloys and Compounds | 2015
Jeoung Han Kim; Thak Sang Byun; Eunjoo Shin; Jae-Bok Seol; Sung Young; N.S. Reddy
Journal of Nuclear Materials | 2015
Young-Ho Lee; Thak Sang Byun
Journal of Nuclear Materials | 2015
Maxim N. Gussev; Thak Sang Byun; Yukinori Yamamoto; S.A. Maloy; Kurt A. Terrani
Journal of Nuclear Materials | 2017
Thak Sang Byun; David T. Hoelzer; Jeoung Han Kim; S.A. Maloy
Journal of Nuclear Materials | 2016
Lance Lewis Snead; Christian I. Contescu; Thak Sang Byun; Wallace D. Porter
Journal of Nuclear Materials | 2017
Timothy G. Lach; Thak Sang Byun; Keith J. Leonard
Environmental Degradation of Materials in Nuclear Power Systems | 2017
Gokul Obulan Subramanian; Sunghoon Hong; Ho Jung Lee; Byeong Seo Kong; Kyoung-Soo Lee; Thak Sang Byun; Changheui Jang