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Gary Lynn Smith

Gary Lynn Smith

Pacific Northwest National Laboratory
PO Box 999
Richland, WA 99352
(509) 372-4220

Biography

Gary L. Smith manages the Glass & Materials Science Technical Team whose research areas include waste form science, non-oxide materials development, commercial glass industry support, and glass & ceramics materials development. As Team Lead, he is responsible for staff development and goals, budget management, and team marketing. In addition, he is currently supporting the Hanford Waste Treatment Plant (vitrification of low- and high-activity radioactive waste) R&T organization, ensuring that the development and use of simulants is coordinated, consistent and defensible across the WTP project and into commissioning. He has managed and was a co-principal investigator of a number of projects that include the following: research on vitrification of low- and high-activity Hanford waste, simulant development and testing of pre-treated low- and high-activity waste and melter feeds, HLW Hanford glass canister qualification activities; and stabilization of DOE complex radioactive salt wastes via sol gel technology. He managed the Materials Characterization Center at the Pacific Northwest National Laboratory, which conducted research leading to the melting of radioactive sludge from West Valley Nuclear Services and analytical round robins of simulated nuclear waste glasses. He led a privately funded study of industrial uses of radioactive materials for heating applications; a vitrification melting study of liquid slurry feeds for the Hanford Waste Vitrification Project; and examination of processability of slurry feeds as a function of batch chemistry for laboratory- and pilot-scale waste vitrification melters; and examination of corrosion of refractory and electrode materials as a function of batch chemistry for use in low-level waste melters.

Dr. Smith has published more than 50 refereed journal articles, technical reports, and conference papers in such journals as the Journal of Non Crystalline Solids, Physics and Chemistry of Glasses and Journal of the American Ceramic Society, as well as a number of classified documents. He has co-edited three Ceramic Transactions volumes dealing with “Environmental and Waste Management Issues in the Ceramic Industry,” published by The American Ceramic Society. He has also given many oral presentations at various technical meetings.

Dr. Smith is a fellow of the American Ceramic Society (ACerS), fellow of ASTM International, and a member of the Materials Research Society. Dr. Smith is past chair of the ACerS Nuclear and Environmental Technology Division, chair of ASTM International Committee C-26 on the Nuclear Fuel Cycle, chair of the Subcommittee C26.13 on Spent Fuel and High Level Waste, and is vice chair of the U.S. Nuclear Technical Advisory Group (NTAG).

Education and Credentials

  • Ph.D. Materials Science & Engineering, University of Arizona, 1993
  • B.A., Chemistry, Occidental College, Los Angeles, CA, 1980

Affiliations and Professional Service

Awards and Recognitions

  • Fellow of American Society of Testing Materials International (ASTM)
  • 2004, Fellow of the American Ceramic Society
  • 2004, Harlan J. Anderson Award, ASTM International Committee C-26 on the Nuclear Fuel Cycle
  • 2004, Chairman of ASTM International Committee C26 on the Nuclear Fuel Cycle

PNNL Publications

2024

  • Kerisit S.N., J.J. Neeway, C.E. Lonergan, B. Parruzot, J. Crum, R.C. Daniel, and G.L. Smith, et al. 2024. "Application of the Immobilized Low-Activity Waste Glass Corrosion Model to the Static Dissolution of 24 Statistically-Designed Alkali-Borosilicate Waste Glasses." Journal of Nuclear Materials 592. PNNL-SA-191827. doi:10.1016/j.jnucmat.2024.154968

2023

  • Asmussen R.M., A.M. Westesen, E. Cordova, A. Fujii Yamagata, P.P. Schonewill, A.C. Moore, and A. Bourchy, et al. 2023. "Iodine Removal from Carbonate-Containing Alkaline Liquids using Strong Base Resins, Hybrid Resins, and Silver Precipitation." Industrial and Engineering Chemistry Research 62, no. 7:3271-3281. PNNL-SA-178096. doi:10.1021/acs.iecr.2c03527
  • Bourchy A., A. Fujii Yamagata, G.L. Smith, G.J. Sevigny, B.N. Seiner, and S.A. Saslow. 2023. "Cerium oxide impact on fresh and hardened properties of cementitious materials." Cement and Concrete Research 138. PNNL-SA-172136. doi:10.1016/j.cemconcomp.2023.104976
  • Neeway J.J., J. Reiser, S.N. Kerisit, R.A. Reyes, R.C. Daniel, G.L. Smith, and R.M. Asmussen, et al. 2023. "Effect of composition on the corrosion behavior of 24 statistically-designed alkali-borosilicate waste glasses." Journal of Nuclear Materials 586. PNNL-SA-185207. doi:10.1016/j.jnucmat.2023.154674

2022

  • Fujii Yamagata A.L., S.A. Saslow, J.J. Neeway, T. Varga, L.R. Reno, Z. Zhu, and K.A. Rod, et al. 2022. "The Behavior of Iodine in Stabilized Granular Activated Carbon and Silver Mordenite in Cementitious Waste Forms." Journal of Environmental Radioactivity 244-245. PNNL-SA-165944. doi:10.1016/j.jenvrad.2022.106824
  • Parruzot B., J. Crum, J. Reiser, J.J. Neeway, S.N. Kerisit, R.C. Daniel, and J.F. Bonnett, et al. 2022. "Effect of zeolite type, temperature, and pH on Stage III glass alteration behavior for two nuclear waste glasses." Journal of Nuclear Materials 567. PNNL-SA-166084. doi:10.1016/j.jnucmat.2022.153717
  • Reiser J., K. Tolman, M. Kropp, R.M. Kissinger, S.A. Saslow, D.A. Cutforth, and J. Crum, et al. 2022. "Fabrication of Radioactive and Non-radioactive Titanate and Zirconate Ceramics for Immobilization of Used Nuclear Fuel." Journal of Nuclear Materials 527. PNNL-SA-171026. doi:10.1016/j.jnucmat.2022.154033
  • Ryan J.V., S.K. Cooley, B. Parruzot, J. Reiser, C.L. Corkhill, J. Du, and K. Ferrand, et al. 2022. Stirred-Reactor Coupon Analysis: An International Round Robin Study. PNNL-33141. Richland, WA: Pacific Northwest National Laboratory. Stirred-Reactor Coupon Analysis: An International Round Robin Study

2021

  • Crum J.V., J. Reiser, B. Parruzot, J.J. Neeway, J.F. Bonnett, S.N. Kerisit, and S.K. Cooley, et al. 2021. "Seeded Stage III Glass Dissolution Behavior of a Statistically Designed Glass Matrix." Journal of the American Ceramic Society 104, no. 8:4145-4162. PNNL-SA-155214. doi:10.1111/jace.17823

2016

2014

  • Smith G.L., C.W. Enderlin, B.E. Wells, D.E. Kurath, and K.M. Denslow. 2014. "Consensus Standardization of Slurry Simulant Development Process to Reduce Design Risk Within the DOE Complex." In WM 2014: 40 Years of Meeting Global Radioactive Waste Management Challenges, March 2-6, 2014, Phoenix, Arizona, Paper No. 14635. Tempe, Arizona:WM Symposia, Inc. PNNL-SA-99586.

2008

  • Bamberger J.A., P.A. Meyer, J.R. Bontha, J.A. Fort, F. Nigl, J.M. Bates, and C.W. Enderlin, et al. 2008. "EVALUATING PULSE JET MIXING WITH NON-NEWTONIAN SLURRIES." In Proceedings of the ASME International Mechanical Engineering Congress and Exposition, IMECE 2007, 8, 1909-1930. New York, New York:American Society Mechanical Engineers. PNWD-SA-7907.

2004

  • Franks C.J., A.P. Quach, D.P. Birnie, W.P. Ela, A.E. Saez, B.J. Zelinski, and H.D. Smith, et al. 2004. "Separation & Fixation of Toxic Components in Salt Brines Using a Water-Based Process." Journal of Undergraduate Research Volume IV, 2004. PNNL-SA-43182.
  • Rengifo F., A.E. Saez, W.P. Ela, A.P. Quach, B. Garbo, C.J. Franks, and B.J. Zelinski, et al. 2004. "Microstructure and Leaching Behavior of Polymer Composites for Encapsulating Toxic Solid Wastes." Industrial and Engineering Chemistry Research 43, no. 23:7492-7499. PNNL-SA-43166.

2003

  • Kukkadapu R.K., H. Li, G.L. Smith, J.V. Crum, J. Jeoung, W. Poisl, and M.C. Weinberg. 2003. "Mossbauer and Optical Spectroscopic Study of Temperature and Redox Effects on Iron Local Environments in a Fe-Doped (0.5 mol% Fe2O3) 18Na(2)O-72SiO(2) Glass." Journal of Non-crystalline Solids 317, no. 3:301-318. PNNL-SA-36181.
  • Smith H.D., G.L. Smith, G. Xia, and B.J. Zelinski. 2003. "Morphology and Composition of Simulant Waste Loaded Polymer Composite Phase Inversion, Encapsulation, and Durability." In Environmental Issues and Waste Management Technologies in the Ceramic and Nuclear Industries VIII: Proceedings of the Symposium held at the 104th Annual Meeting of The American Ceramic Society, April 28-May 1, 2002 in St. Louis, Missouri. Ceramic Transactions, edited by SK Sundaram, DR Spearing and JD Vienna, 143, 371-376. Westerville, Ohio:The American Ceramic Society. PNNL-SA-37667.

2002

  • Palmer R.A., H.D. Smith, G.L. Smith, M.R. Smith, R.L. Russell, and G.K. Patello. 2002. "Chemical and Physical Characterization of the First West Valley Demonstration Project High-Level Waste Feed Batch." In Environmental Issues & Waste Management Technologies in the Ceramic & Nuclear Industries VII: Proceedings - Science & Technology in Addressing Environmental Issues in the Ceramic Industry and the Ceramic Science & Technology for the Nuclear Industry Symposiums; 103rd Annual Meeting, American Ceramic Society, April 22-25, 2001, Indianapolis, IN.: Ceramic Transactions, edited by DR Spearing, GL Smith and SK Sundaram, 132. Westerville, Ohio:The American Ceramic Society. PNNL-SA-35400. doi:10.1002/9781118371435.ch33
  • Smith G.L., H.D. Smith, M.J. Schweiger, and D.J. Bates. 2002. "Vitrification and Testing of Hanford Pretreated HLW Sludge Mixed with Flowsheet Quantities of Secondary Wastes." In Science and Technology in Addressing Environmental Issues in the Ceramic Industry; Environmental Issues and Waste Management Technologies in the Ceramic and Nuclear Industries VII: Ceramic Transactions, edited by GL Smith, SK Sundaram, DR Spearing, 132, 117-128. Westerville, Ohio:American Ceramic Society. PNWD-SA-5380.
  • Smith G.L., H.D. Smith, M.J. Schweiger, and G.F. Piepel. 2002. "Vitrification and Testing of Hanford Pretreated Low Activity Waste." In Environmental Issues and Waste Management Technologies in the Ceramic and Nuclear Industries VII, proceedings, 103rd Annual Meeting of The American Ceramic Society, held April 22-25, 2001, in Indianapolis, Indiana, USA., edited by Gary L. Smith, S.K. Sundaram, and Dane R. Spearing, 132, 129-140. Westerville, Ohio:The American Ceramic Society. PNWD-SA-5379.

2001

  • Jeoung J., W. Poisl, M.C. Weinberg, G.L. Smith, and H. Li. 2001. "Effect of Oxidation State of Iron on Phase Separation in Sodium Silicate Glasses." Journal of the American Ceramic Society 84, no. 8:1859-1864. PNWD-SA-4657.
  • Terry T.N., R.L. Russell, H.D. Smith, L. Liang, and G.L. Smith. 2001. "Aqueous-Based Latex Systems for Producing Durable Waste Forms-Initial Characterization." Journal of Undergraduate Research 1. PNNL-SA-33570.

1998

  • Smith G.L., and H.D. Smith. 1998. "Fabrication and Characterization of a Fully Loaded High Level Waste Glass." In Environmental Issues and Waste Management Technologies in the Ceramic and Nuclear Industries III, Ceramic Transactions, edited by D.K. Peeler and J.C. Marra, 87, 325-334. Westerville, Ohio:The American Ceramic Society. PNNL-SA-29070.

Energy and Environment

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