Senior Staff Scientist
Research Areas: Materials Characterization; Plasma-surface interactions; Radiation interaction with materials
Biography: Dr. Chase N. Taylor joined the Fusion Safety Program at Idaho National Laboratory in 2012. Dr. Taylor’s research areas focus on hydrogen isotope behavior, refractory metals, radiation interaction with materials, plasma physics, and materials characterization. Current research investigates tritium retention in neutron activated plasma facing components for magnetic fusion energy. He holds expertise in numerous material evaluation techniques, and during his time at INL has built up a surface science characterization laboratory at the Safety and Tritium Applied Research (STAR) laboratory. These materials characterization capabilities include glow discharge optical emission spectroscopy (GD-OES), X-ray photoelectron spectroscopy (XPS), thermal desorption spectroscopy (TDS), scanning electron/Auger microscopy (SEM), and positron annihilation spectroscopy (PAS), among others. Dr. Taylor acts as an INL principle researcher and has over 45 journal publications and over 500 citations. Dr. Taylor sits on the Executive Committee for the American Nuclear Society Fusion Energy Division. He has also served as a guest editor for the journal, Fusion Engineering and Design. Dr. Taylor is fluent in Spanish and enjoys backpacking, skiing, and spending time with his family.
Google Scholar ResearchGate ORCID
Ph.D., Nuclear Engineering - Purdue University
M.S., Nuclear Engineering - Purdue University
B.S., Mechanical Engineering - Idaho State University
W. Streit Cunningham, Jonathan M. Gentile, Osman El-Atwani, Chase N. Taylor, Mert Efe, Stuart A. Maloy, and Jason R. Trelewicz, “Softening due to Grain Boundary Cavity Formation and its Competition with Hardening in Helium Implanted Nanocrystalline Tungsten” Scientific Reports, (2018) 8:2897.
O. El-Atwani, C.N. Taylor, J. Krishoff, W. Harlow, M. Efe, M.L. Taheri, “Thermal desorption spectroscopy of high fluence irradiated ultrafine and nanocrystalline tungsten: Helium trapping and desorption correlated with morphology” Nuclear Fusion, Nuclear Fusion 58 (2018) 016020.
C.N. Taylor and M. Shimada, “Direct depth distribution measurement of deuterium in bulk tungsten exposed to high-flux plasma”, AIP Advances, 7 (2017) 055305.
C.N. Taylor, M. Shimada, B.J. Merrill, D.W. Akers, Deuterium retention and blistering in tungsten foils, Nuclear Materials and Energy 12 (2017), 689-693.
M. Shimada, C.N. Taylor, R. Pawelko, L.C. Cadwallader, B.J. Merrill, “Tritium Plasma Experiment Upgrade and Improvement of Surface Diagnostic Capabilities at STAR Facility for Enhancing Tritium and Nuclear PMI Sciences” Fusion Science and Technology, 71:2 (2017) 310-315.
C.N. Taylor, Y. Yamauchi, M. Shimada, Y. Oya, Y. Hatano, “Deuterium retention in helium and neutron irradiated molybdenum” Fusion Science and Technology, 7 (2017) 491-495.
M. Shimada, C.N. Taylor, L. Moore-McAteer, R.J. Pawelko, R.D. Kolasinski, D.A. Buchenauer, B.J. Merrill, “TPE upgrade for improving in-vessel tritium inventory assessment in fusion nuclear environment” Fusion Engineering and Design, 109-111 (2016) 1077-1081.
C.N. Taylor, M. Shimada, B.J. Merrill, D.W. Akers, Y. Hatano, “Development of positron annihilation spectroscopy for investigating deuterium decorated voids in neutron-irradiated tungsten” Journal of Nuclear Materials, 463 (2015) 1009–1012.
C.N. Taylor, J.P. Allain, K.E. Luitjohan, P.S. Krstic, J. Dadras, and C.H. Skinner, “Differentiating the role of oxygen and lithium in retaining deuterium on lithiated graphite plasma-facing components” Physics of Plasmas, 21, 057101 (2014).
C.N. Taylor, M. Shimada, B.J. Merrill, M.W. Drigert, D.W. Akers, Y. Hatano, “Development of positron annihilation spectroscopy for characterizing neutron irradiated tungsten” Physica Scripta, T159 (2014) 014055.
C.N. Taylor, J.P. Allain, K.E. Luitjohan, P.S. Krstic, J. Dadras, and C.H. Skinner, “The role of oxygen in retaining deuterium on lithiated graphite surfaces” J. Appl. Phys., 114, 223301 (2013).