PNNL

Gary L. Smith joined Pacific Northwest National Laboratory (PNNL) in 1993. Smith has over 30 years of experience in managing projects and staff at a variety of levels, as well as developing scope to close technical gaps within the nuclear fuel cycle in the United States and their associated resource-loaded schedules and budgets while mitigating risks, which have been managed for on-time delivery and within budget. His professional background includes project and line management experience at PNNL, a four-year long off-site assignment to the Office of Waste Processing, Office of Environmental Management, and a six-year long off-site assignment to the Hanford Waste Treatment Plant Research and Technology and Process Engineering and Technology Organizations.

His recent experience includes working with the Washington River Protection Solutions Chief Technical Office as the project manager for PNNL’s Hanford Site Low‑Activity Waste Form Development Integrated Disposal Facility performance assessment maintenance support efforts. As part of this effort Smith supports the technical basis for the integrated disposal facility that will accept Hanford low-level waste forms for disposal with a high level of quality assurance rigor. This includes teaming with and collaborating with the Vitreous State Laboratory at The Catholic University, Savannah River National Laboratory, and the National Laboratories Consortium (e.g., Sandia, Los Alamos, etc.).

Smith’s past line management experience includes management of the Glass and Materials Science technical team and the acting technical group manager for the Radiological Materials and Detection group, which included four technical teams whose research areas included waste form science, non‑oxide materials development, commercial glass industry support, and glass and ceramics materials development mainly supporting the U.S. nuclear fuel cycle. Smith’s line management duties included managing staff to assure effective communication across the technical group and teams. He was responsible for staff members’ career development and goals, budget management, and team marketing, assuring effective communication and recruiting.

Smith has published more than 100 refereed journal articles, technical reports, and conference papers in such journals as the Journal of Nuclear Materials, Journal of Non-Crystalline Solids, Physics and Chemistry of Glasses Journal of the American Ceramic Society, Journal of Environmental Radioactivity, Cement and Concrete Research, Cement and Concrete Composites, Journal of Hazardous Materials, and Industrial & Engineering Chemistry Research, as well as many classified documents. He has coedited three Ceramic Transactions volumes on “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

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

• Material sciences
• Waste management and disposal
• Nuclear waste forms development and testing (glass, glass ceramics, ceramics, cementitious (grout))
• Nuclear waste streams processing flowsheets
• Project management
• Line management

• PhD in materials science and engineering, University of Arizona
• BS in chemistry, Occidental College

• American Ceramic Society
• Materials Research Society
• ASTM International

• Harlan J. Anderson Award, ASTM International Committee C26 on the Nuclear Fuel Cycle, 2004
• ASTM International Fellow

• Fellow of the American Ceramic Society, 2004
• Chair, ASTM International Committee C26 on the Nuclear Fuel Cycle, 2004 – 2009
• Chair, ASTM International Subcommittee C26.13 on Nuclear Waste

2023

• Asmussen R.M., A.M. Westesen, E. Cordova, A. Fujii Yamagata, P.P. Schonewill, A.C. Moore, and A. Bourchy, Sarah A. Saslow, Gary L. Smith, Brian J. Riley, and Rodney S. Skeen. 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, Benjamin P. Parruzot, and Jarrod V. Crum. 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
• Asmussen, R. Matthew, Amy Westesen, Elsa A. Cordova, Alessandra Lie Fujii Yamagata, Philip P. Schonewill, Aryiana C. Moore, Agathe Bourchy, Sarah A. Saslow, Gary L. Smith, Brian J. Riley, and Rodney S. Skeen. 2023. “Iodine Removal from Carbonate-Containing Alkaline Liquids Using Strong Base Resins, Hybrid Resins, and Silver Precipitation” - Industrial & Engineering Chemistry Research DOI: 10.1021/acs.iecr.2c03527.
• Agathe Bourchy, Alessandra L. Fujii Yamagata, Gary L. Smith, Gary J. Sevigny, Brienne N. Seiner, Sarah A. Saslow. 2023. “Cerium oxide impact on fresh and hardened properties of cementitious materials” Cement and Concrete Composites, Vol. 138 https://doi.org/10.1016/j.cemconcomp.2023.104976

2022

• Bourchy A., S.A. Saslow, B.D. Williams, N.M. Avalos, W. Um, N.L. Canfield, L.E. Sweet, G.L. Smith, and R.M. Asmussen. 2022. "The evolution of hydrated lime-based cementitious waste forms during leach testing leading to enhanced technetium retention." Journal of Hazardous Materials 430. PNNL-SA-165711. doi:10.1016/j.jhazmat.2022.128507
• Fujii Yamagata A.L., S.A. Saslow, J.J. Neeway, T. Varga, L.R. Reno, Z. Zhu, K.A. Rod, B.R. Johnson, J.A. Silverstein, J.H. Westsik, G.L. Smith, and R.M. Asmussen. 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
• Bourchy A., S.A. Saslow, B.D. Williams, N.M. Avalos, W. Um, N.L. Canfield, L.E. Sweet, G.L. Smith, and R.M. Asmussen. 2022. "The evolution of hydrated lime-based cementitious waste forms during leach testing leading to enhanced technetium retention." Journal of Hazardous Materials 430. PNNL-SA-165711. doi:10.1016/j.jhazmat.2022.128507
• Parruzot B., J. Crum, J. Reiser, J.J. Neeway, S.N. Kerisit, R.C. Daniel, J.F. Bonnett, R.A. Reyes, L.M. Seymour, C.A.M. Burns, R.V. Ryan, G.L. Smith, and R.M. Asmussen. 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, J. Crum, Brienne N. Seiner, Gary L. Smith, and John D. Vienna. 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, K. Ferrand, S. Gin, M.T. Harrison, Y. Inagaki, C. Lenting, J.S. McCloy, S. Mitsui, M.M.V. Snyder, N.J. Smith, R.M. Asmussen, and G.L. Smith. 2022. Stirred-Reactor Coupon Analysis: An International Round Robin Study. PNNL-33141. RPT-IGTP-027, Rev. 0. 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, S.K. Cooley, Joseph V. Ryan, Gary L. Smith, R. Matthew Asmussen. 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

• Smith G.L. 2016. Waste Form Release Data Package for the 2005 Integrated Disposal Facility Performance Assessment, Erratum. PNNL-14805 Erratum. Richland, WA: Pacific Northwest National Laboratory. doi:10.2172/1326161.Waste Form Release Data Package for the 2005 Integrated Disposal Facility Performance Assessment, Erratum

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.

1994

• Smith G.L., and M.C. Weinberg. 1994. "Experimental Test of Surface Nucleated Crystal Growth Model in Lithium Diborate Glass," Phys. Chem. Glasses, 35(1), 6-9

1993

• Denesuk, M, G.L. Smith, B.J.J. Zelinski, N.J. Kreidl, and D.R. Uhlmann. 1993. "Capillary Penetration of Liquid Droplets into Porous Materials," J. of Colloid and Interface Science, 158, 114-120,

1991

• Smith G.L., and M.C. Weinberg. 1991. "Crystal Nucleation in Lithium Diborate Glass," Phys. Chem. of Glasses 32(2), 37-42.

1987

• Smith G.L., G.F. Neilson and M.C. Weinberg. 1991. "Crystal Nucleation in Lithium Borate Glass," Phys. Chem. of Glasses 28(6), 257.

1986

• Neilson, G.F., M.C. Weinberg, and G.L. Smith. 1986. "Effect of OH Content on Phase Separation Behavior of Soda-Silica Glasses," J. Non-Cryst. Solids 82, 137.

1985

• Neilson, G.F., G.L. Smith, and M.C. Weinberg. 1985. "The Effect of Chloride Incorporation on the Crystallization of a Zirconium-Barium-Lanthanum-Aluminum Fluoride Glass," J. Am. Cer. Soc. 68(11), 629.
• Weinberg, M.C., G.F. Neilson, G.L. Smith, B. Dunn, G.S. Moore, and J.D. Mackenzie, 1985. "The Preparation and Characterization of a Lithium Borate Glass Prepared by the Gel Technique," J.  Mater. Sci. 20(4), 1501.

1984

• Neilson, G.F., G.L. Smith, and M.C. Weinberg. 1984. "The Crystallization Behavior and Kinetics of Barium Fluorozirconate Based Glasses," Mat. Res. Bull. 19, 279.

1983

• Weinberg, M.C., G.F. Neilson, and G.L. Smith. 1983. ""Crystallization of Barium Fluorozirconate Based Glasses," J. Non-Cryst. Solids 56, 45.