| Masashi Shimada | | Leading Principal Investigator at the Safety and Tritium Applied Research (STAR) facility at INL in support of the DOE Fusion Energy Science tritium and safety research. Principal Investigator of the Tritium Plasma Experiment (TPE), Tritium Lead Lithium Eutectic (TLLE) experiment, and the Tritium
Heat eXchanger experiment (THX). Conducts experiments and numerical modeling of hydrogen isotope permeation, especially tritium, and transport in materials for fusion applications as well as for the DOE Nuclear Energy (NE) Very High Temperature Reactor (VHTR) fission plant design. Serves as the Task 1 (In-Vessel Tritium Source Term) coordinator for the International Energy Agency (IEA) Implementing Agreement on the Environmental, Safety and Economic Aspects of Fusion Power (ESE-FP). PhD in Engineering Physics from the University of California-San Diego. Joined INL in 2007.
| 208-533-4472 | Email Contact |  | | Robert Pawelko | | Scientist in the Fusion Safety Program. Investigates tritium permeation in high temperature alloys. Responsible for tritium accountability measurements and documentation and assists in general laboratory activities at the STAR lab. Knowledgeable in tritium accountancy and tritium measurement systems, quadrupole mass spectrometry, BET surface area measurements, elemental assay by prompt gamma neutron activation analysis, and radiation measurements and spectrometry. Supports tasks in hydrogen isotope transport in fusion relevant material studies, beryllium dust explosion studies, beryllium-steam reactivity studies, tritium recovery from irradiated beryllium research, waste characterization, getter applications, and radiation monitoring systems. B.S. in physics from Northeastern Illinois University. Worked at INL since 1989. | 208-533-4792 | Email Contact |  | | Chase Taylor | | Experimental researcher with expertise in hydrogen retention, plasma material interactions, fusion technology, surface chemistry analysis techniques, vacuum systems. Research interests include tritium retention in neutron damaged refractory materials, techniques for measuring defect concentration, and tritium permeation. Principal researcher for STAR surface characterization equipment, including glow discharge optical emission spectroscopy (GD-OES), X-ray photoelectron spectroscopy (XPS), scanning Auger microprobe (SAM), positron annihilation spectroscopy (PAS), and thermal desorption spectroscopy (TDS). Operates the neutron irradiated material ion implantation experiment (NIMIIX) focusing on deuterium ion implantation. Conducts thermal desorption spectroscopy and positron annihilation spectroscopy. PhD in nuclear engineering from Purdue University. Joined INL in 2012. | 208-533-4068 | Email Contact |  | | Tommy Fuerst | | Researcher specialized in hydrogen membrane technology, hydrogen transport and permeation, thin-film deposition, and surface analysis. Research interests include fusion fuel cycle technology such as tritium extraction from breeder blanket systems and superpermeable membranes for torus exhaust pumping and separation, multiphase mass transport, systems analysis, and tritium issues and mitigation in molten salt reactors. He joined INL in 2019 after completing his PhD in Chemical Engineering from the Colorado School of Mines and BS in Chemical Engineering from University of Colorado Boulder. When not researching tritium, he can be found in the local mountains rock climbing and skiing with his wife Meriel.
| 208-533-4399 | Email Contact |  | | Adriaan Riet | | Adriaan received a BS in Chemical Engineering from BYU in 2015 and a PhD from Case Western Reserve University in 2020. He has been involved in research projects related to cryogenic carbon capture, micron-scale battery characterization and self-charging particle adhesion. His thesis addressed transport properties of materials under the conditions of the earth's core-mantle boundary using molecular dynamics simulations. He currently works within the AGR program investigating the transport of fission products in nuclear-grade graphites with data from the AGR-3/4 experiments.
| | Email Contact |  | | Matthew Eklund | | Matthew is a
postdoctoral researcher specializing in computational modeling and simulation
for nuclear reactor systems. He is currently involved in the Fusion Safety
Program in the development of the MELCOR-TMAP code for modeling and simulation
of fusion systems performance and accident scenarios. His previous research has
been focused on neutronics and thermal-hydraulics analysis of fission reactor
systems and the development of a set of benchmarks based on
temperature-dependent critical experiments performed at the Walthousen Reactor
Critical Facility (RCF) owned and operated by Rensselaer Polytechnic Institute.
He received a B.S. in Mechanical Engineering and M.S. in Nuclear Engineering
from The University of Utah and a Ph.D. in Nuclear Engineering & Science
from Rensselaer Polytechnic Institute. Matthew joined INL as an intern in 2015
after completing his research for his master’s degree and as a postdoctoral
researcher in 2021. His interests include philosophy, theology, science fiction
and fantasy novels, art, and computer gaming.
| | Email Contact |  |
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