PNNL

Harold Adkins serves as a subject matter expert and consultant on the development of the Project Pele Transportable Reactor for the Department of Defense Strategic Capabilities Office. He also currently serves as PNNL’s technology expert for the liquid metal magnetohydrodynamic-based annular linear induction pump, with over 30 years of experience in this field. 

Adkins has been sought out to support the National Nuclear Security Administration (NNSA), Jet Propulsion Laboratory, and NASA’s Fission Surface Power Program regarding the analysis, design, development, construction, and testing of liquid metal pump and cooling systems. He has over 29 years of experience in packaging, transportation, and storage of Type B radioactive material. His current work includes providing technical leadership and program management for the Nuclear Regulatory Commission (NRC), Department of Energy Offices of Nuclear Energy and Environmental Management, and NNSA. He serves as principal investigator in support of performance of structural and thermal independent analytical evaluations of U.S. design agents’ packaging-related safety analysis submittals for both the NRC and the NNSA. He has provided over two decades of leadership in the performance of beyond-regulatory and survivability assessments and retrievability threshold evaluations of selected certified spent nuclear fuel transport systems to aid in accident-mitigation-related rulemaking to enhance public safety.

He has recently been engaged to identify a regulation set applicable to road, rail, and air transport of small mobile nuclear reactors (similar to Type C regulations). He serves as principal investigator and key structural and thermal contributor for the design, development, construction, commissioning, and deployment of the Defense Programs Package (DPP)-3. Previous work includes design, development, analysis, construction, and commissioning of a majority of PNNL’s full-scale test platforms, with emphasis in the areas of multi-phase fluid flow evaluation, heat transfer, and feed separation applied to nuclear processes and facilities. Some of this work supports research and development programs revolving around Hanford legacy waste dispositioning and safety basis development.

• MS, mechanical engineering, University of Wyoming
• BS, mechanical engineering, University of Wyoming

2022

Coles G.A., P.P. Lowry, J.R. Phillips, S.M. Short, C.A. Condon, S.J. Maheras, and T.A. Ikenberry, et al. 2022. Parametric Study of Factors that Affect Calculated Dose from TRISO Fueled Microreactor Transportation Accident. PNNL-33607. Richland, WA: Pacific Northwest National Laboratory. Parametric Study of Factors that Affect Calculated Dose from TRISO Fueled Microreactor Transportation Accident

Coles G.A., S.M. Short, S.J. Maheras, and H.E. Adkins. 2022. "Risk-Informed Approach for Regulatory Approval of Microreactor Transport." In Proceedings of the 16th International Conference on Probabilistic Safety Assessment and Management (PSAM 2022), June 26-July 1, 2022, Honolulu, HI. Los Angeles, California:International Association for Probabilistic Safety Assessment and Management. PNNL-SA-172477.

2021

Eidelpes E., B.M. Hom, R. Hall, H.E. Adkins, and J. Jarrell. 2021. "A High-Assay Low-Enriched Uranium Fuel Transportation Concept." Nuclear Science and Engineering 195, no. 3:279-299. PNNL-SA-156769. doi:10.1080/00295639.2020.1802161

2015

Meyer R.M., J.M. Cuta, A.M. Jones, K.M. Denslow, P. Ramuhalli, H.E. Adkins, and B.D. Hanson. 2015. "Feasibility of Acoustic Methods for Impurity Gas Monitoring in Dry Storage Systems." In 15th International High-Level Radioactive Waste Management Conference, April 12-16, 015, Charleston, South Carolina, 829-834. Lagrange Park, Illinois:American Nuclear Society. PNNL-SA-107377.

2014

Cuta J.M., and H.E. Adkins. 2014. Preliminary Thermal Modeling of HI-STORM 100 Storage Modules at Diablo Canyon Power Plant ISFSI. PNNL-23298. Richland, WA: Pacific Northwest National Laboratory. Preliminary Thermal Modeling of HI-STORM 100 Storage Modules at Diablo Canyon Power Plant ISFSI

Geelhood K.J., H.E. Adkins, S.E. Sanborn, B.J. Koeppel, and N.A. Klymyshyn. 2014. "Analytical Model Methodology Development and Demonstration of Approach on Used Fuel Performance Characterization for Condition of Normal Transportation." In Annual Waste Management Symposium (WM 2014) March 2 - 6, 2014, Phoenix, Arizona,, 7, 5646-5668. Tucson, Arizona:Waste Management Symposia, Inc. PNNL-SA-100268.

Restivo M.L., M.E. Stone, D.T. Herman, D.P. Lambert, M.R. Duignan, G.L. Smith, and B.E. Wells, et al. 2014. Technology Evaluation for Conditioning of Hanford Tank Waste Using Solids Segregation and Size Reduction. PNNL-23030. Richland, WA: Pacific Northwest National Laboratory. Technology Evaluation for Conditioning of Hanford Tank Waste Using Solids Segregation and Size Reduction

Sanborn S.E., B.J. Koeppel, K.J. Geelhood, and H.E. Adkins. 2014. "Sensitivity Studies on UNF Cladding Structural Integrity under NCT Loading." Transactions of the American Nuclear Society 111. PNNL-SA-104385.

2013

Adkins H.E., J.A. Fort, S.R. Suffield, J.M. Cuta, and B.A. Collins. 2013. "Thermal Modeling Studies for Active Storage Modules in the Calvert Cliffs ISFSI." In 14th International High-Level Radioactive Waste Management Conference (IHLRWMC 2013): Integrating Storage, Transportation, and Disposal, April 28-May 2, 2013, Albuquerque, New Mexico, 2, 999-1004. Pittsburgh, Pennsylvania:Air and Waste Management Association. PNNL-SA-92645.

Bontha J.R., P.A. Gauglitz, D.E. Kurath, H.E. Adkins, C.W. Enderlin, J. Blanchard, and R.C. Daniel, et al. 2013. "Experimental Challenges and Successes in Measuring Aerosol Concentrations at Prototypic Spray Conditions Encountered at the Hanford Waste Treatment and Immobilization Plant - 13327." In Waste Management Symposia (WM2013): International Collaboration and Continuous Improvement, February 24-28, 2013, Phoenix, Arizona. Tempe, Arizona:WM Symposia. PNNL-SA-92681.

Cuta J.M., and H.E. Adkins. 2013. Preliminary Thermal Modeling of HI-Storm 100S-218 Version B Storage Modules at Hope Creek Nuclear Power Station ISFSI. PNNL-22552; FCRD-UFD-2013-000297. Richland, WA: Pacific Northwest National Laboratory. Preliminary Thermal Modeling of HI-Storm 100S-218 Version B Storage Modules at Hope Creek Nuclear Power Station ISFSI

Cuta J.M., and H.E. Adkins. 2013. Preliminary Thermal Modeling of Hi-Storm 100S-218 Version B Storage Modules at Hope Creek Nuclear Power Station ISFSI. PNNL-22552 Rev. 1. Richland, WA: Pacific Northwest National Laboratory. Preliminary Thermal Modeling of Hi-Storm 100S-218 Version B Storage Modules at Hope Creek Nuclear Power Station ISFSI

Cuta J.M., S.R. Suffield, J.A. Fort, and H.E. Adkins. 2013. Thermal Performance Sensitivity Studies in Support of Material Modeling for Extended Storage of Used Nuclear Fuel. PNNL-22646. Richland, WA: Pacific Northwest National Laboratory. Thermal Performance Sensitivity Studies in Support of Material Modeling for Extended Storage of Used Nuclear Fuel

Denslow K.M., J.R. Bontha, H.E. Adkins, J.W. Jenks, D.F. Hopkins, M.G. Thien, and S.E. Kelly, et al. 2013. "System Performance Testing of the Pulse-Echo Ultrasonic Instrument for Critical Velocity Determination during Hanford Tank Waste Transfer Operations - 13584." In Annual Waste Management Symposium (WM2013): International Collaboration and Continuous Improvement, February 24-28, 2013, Phoenix, Arizona, 7, 5916-5938. Tempe, Arizona:WM Symposia. PNNL-SA-92964.

Klymyshyn N.A., H.E. Adkins, C.S. Bajwa, and J. Piotter. 2013. "Package Impact Models as a Precursor to Cladding Analysis." Journal of Pressure Vessel Technology 135, no. 1:Article No. 011601. PNNL-SA-87876. doi:10.1115/1.4007469

Klymyshyn N.A., N.K. Karri, H.E. Adkins, and B.D. Hanson. 2013. Structural Sensitivity of Dry Storage Canisters. PNNL-22814. Richland, WA: Pacific Northwest National Laboratory. Structural Sensitivity of Dry Storage Canisters

Klymyshyn N.A., S.E. Sanborn, H.E. Adkins, and B.D. Hanson. 2013. Fuel Assembly Shaker Test Simulation. PNNL-22507. Richland, WA: Pacific Northwest National Laboratory. Fuel Assembly Shaker Test Simulation

Meyer R.M., A.F. Pardini, J.M. Cuta, H.E. Adkins, A.M. Casella, H. Qiao, and M.R. Larche, et al. 2013. NDE to Manage Atmospheric SCC in Canisters for Dry Storage of Spent Fuel: An Assessment. PNNL-22495. Richland, WA: Pacific Northwest National Laboratory. NDE to Manage Atmospheric SCC in Canisters for Dry Storage of Spent Fuel: An Assessment

2012

Bajwa C.S., E.P. Easton, H.E. Adkins, J.M. Cuta, N.A. Klymyshyn, and S.R. Suffield. 2012. "The MacArthur Maze Fire and Roadway Collapse: A "Worst Case Scenario" for Spent Nuclear Fuel Transportation?." In ASME 2012 Pressure Vessels and Piping Division Conference (PVP 2012), July 15-19, 2012, Toronto, Ontario, Canada, 7, 261-269. New York:American Society of Mechanical Engineers. PNNL-SA-88983. doi:10.1115/PVP2012-78637

Denslow K.M., J.R. Bontha, H.E. Adkins, J.W. Jenks, and D.F. Hopkins. 2012. Hanford Tank Farms Waste Feed Flow Loop Phase VI: PulseEcho System Performance Evaluation. PNNL-22029. Richland, WA: Pacific Northwest National Laboratory. Hanford Tank Farms Waste Feed Flow Loop Phase VI: PulseEcho System Performance Evaluation

Denslow K.M., J.R. Bontha, H.E. Adkins, J.W. Jenks, C.A. Burns, P.P. Schonewill, and D.F. Hopkins, et al. 2012. "Continued Evaluation of the Pulse-Echo Ultrasonic Instrument for Critical Velocity Determination during Hanford Tank Waste Transfer Operations." In Waste Management Symposium (WM 2012): Improving the Future in Waste Management, February 26-March 1, 2012, Phoenix, Arizona, Paper No. 12518. Tucson, Arizona:Waste Management Symposia Inc. PNNL-SA-85110.

Fountain M.S., J. Blanchard, R.L. Erikson, D.E. Kurath, D.T. Howe, H.E. Adkins, and J.W. Jenks. 2012. "Design of a Particle Shadowgraph Velocimetry and Size (PSVS) System to Determine Particle Size and Density Distributions (PSDD) in Hanford Nuclear Tank Wastes." In Waste Management Symposium (WM 2012): Improving the Future in Waste Management, February 26 - March 1, 2012, Phoenix, Arizona, Paper No. 12280. Tucson, Arizona:Waste Management Symposia, Inc. PNNL-SA-85041.

Schonewill P.P., P.A. Gauglitz, J.R. Bontha, R.C. Daniel, D.E. Kurath, H.E. Adkins, and J.M. Billing, et al. 2012. Large-Scale Spray Releases: Initial Aerosol Test Results. PNNL-21333; WTP-RPT-217 Rev.0. Richland, WA: Pacific Northwest National Laboratory. Large-Scale Spray Releases: Initial Aerosol Test Results

Suffield S.R., J.A. Fort, H.E. Adkins, J.M. Cuta, B.A. Collins, and E.R. Siciliano. 2012. Thermal Modeling of NUHOMS HSM-15 and HSM-1 Storage Modules at Calvert Cliffs Nuclear Power Station ISFSI. PNNL-21788. Richland, WA: Pacific Northwest National Laboratory. Thermal Modeling of NUHOMS HSM-15 and HSM-1 Storage Modules at Calvert Cliffs Nuclear Power Station ISFSI

2011

Bajwa C.S., E.P. Easton, H.E. Adkins, J.M. Cuta, N.A. Klymyshyn, and S.R. Suffield. 2011. "Effects of the MacArthur Maze Fire and Roadway Collapse on a Spent Nuclear Fuel Transportation Package." In WM 2011: Global Achievements and Challenges in Waste Management. 37th Annual Waste Management Symposium, February 27 - March 3, 2011, Phoenix, Arizona, Paper No. 11392. Tucson, Arizona:WM Symposia. PNNL-SA-76810.

Bontha J.R., K.M. Denslow, H.E. Adkins, J.W. Jenks, C.A. Burns, P.P. Schonewill, and G.P. Morgen, et al. 2011. "Evaluation of Three Ultrasonic Instruments for Critical Velocity Determination during Hanford Tank Waste Transfer Operations - 11121." In 37th Annual Radioactive Waste Management Symposium (WM 2011): Global Achievements and Challenges in Waste Management, February 27-March 3, 2011, Phoenix, Arizona, 5, 3999-4013. Tempe, Arizona:WM Symposia. PNNL-SA-77135.

2010

Bajwa C.S., J. Piotter, J.M. Cuta, H.E. Adkins, N.A. Klymyshyn, J.A. Fort, and S.R. Suffield. 2010. "Best Practices for Finite Element Analysis of Spent Nuclear Fuel Transfer, Storage, and Transportation Systems." In Proceedings of the 51st Annual Meeting of the Institute of Nuclear Materials Management, July 11-15, 2010, Baltimore, Maryland. Deerfield, Illinois:INMM. PNNL-SA-73385.

Bamberger J.A., P.A. Meyer, P.A. Scott, H.E. Adkins, B.E. Wells, J. Blanchard, and K.M. Denslow, et al. 2010. Hanford Tank Farms Waste Certification Flow Loop Test Plan. PNNL-18936. Richland, WA: Pacific Northwest National Laboratory. Hanford Tank Farms Waste Certification Flow Loop Test Plan

Bontha J.R., J.W. Jenks, G.P. Morgen, T.J. Peters, W.A. Wilcox, H.E. Adkins, and C.A. Burns, et al. 2010. Test Loop Demonstration and Evaluation of Slurry Transfer Line Critical Velocity Measurement Instruments. PNNL-19441 Rev. 0. Richland, WA: Pacific Northwest National Laboratory. Test Loop Demonstration and Evaluation of Slurry Transfer Line Critical Velocity Measurement Instruments

Klymyshyn N.A., H.E. Adkins, C. Bajwa, and J. Piotter. 2010. "Package Impact Models as a Precursor to Cladding Analysis." In ASME 2010 Pressure Vessels and Piping Conference, July 18-22, 2010, Bellevue, Washington, 7, 507-513. New York, New York:ASME. PNNL-SA-71294. doi:10.1115/PVP2010-25773

Poloski A.P., A.W. Etchells, J. Chun, H.E. Adkins, A.M. Casella, M.J. Minette, and S.T. Yokuda. 2010. "A Pipeline Transport Correlation for Slurries with Small but Dense Particles." Canadian Journal of Chemical Engineering 88, no. 2:182-189. PNNL-SA-65163.

2009

Poloski A.P., H.E. Adkins, J. Abrefah, A.M. Casella, R.E. Hohimer, F. Nigl, and M.J. Minette, et al. 2009. Deposition Velocities of Newtonian and Non-Newtonian Slurries in Pipelines. PNNL-17639. Richland, WA: Pacific Northwest National Laboratory. Deposition Velocities of Newtonian and Non-Newtonian Slurries in Pipelines

Poloski A.P., M.L. Bonebrake, A.M. Casella, M.D. Johnson, J.J. Toth, H.E. Adkins, and J. Chun, et al. 2009. Deposition Velocities of Non-Newtonian Slurries in Pipelines: Complex Simulant Testing. PNNL-18316. Richland, WA: Pacific Northwest National Laboratory. Deposition Velocities of Non-Newtonian Slurries in Pipelines: Complex Simulant Testing

Yokuda S.T., A.P. Poloski, H.E. Adkins, A.M. Casella, R.E. Hohimer, N.K. Karri, and M. Luna, et al. 2009. A Qualitative Investigation of Deposition Velocities of a Non-Newtonian Slurry in Complex Pipeline Geometries. PNNL-17973; WTP-RPT-178 Rev. 0. Richland, WA: Pacific Northwest National Laboratory. A Qualitative Investigation of Deposition Velocities of a Non-Newtonian Slurry in Complex Pipeline Geometries

2007

Shah M.J., N.A. Klymyshyn, H.E. Adkins, and B.J. Koeppel. 2007. "HI-STAR 100 Spent Fuel Transport Cask Analytical Evaluation for Drop Events." Packaging, Transport, Storage and Security of Radioactive Material 18, no. 1:3-9. PNNL-SA-54365.

Shah M.J., N.A. Klymyshyn, H.E. Adkins, and B.J. Koeppel. 2007. "TN-68 Spent Fuel Transport Cask Analytical Evaluation for Drop Events." Packaging, Transport, Storage and Security of Radioactive Material 18. PNNL-SA-54285.

2005

Adkins H.E. 2005. "Application of Annular Linear Induction Pumps Technology for Waste Heat Rejection and Power Conversion." In Space Nuclear Conference 2005 (SNC '05), June 5-9, 2005, San Diego, California, 714-722. La Grange Park, Illinois:American Nuclear Society. PNNL-SA-44540.

2004

Adkins H.E., B.J. Koeppel, and D.T. Tang. 2004. "Spent Nuclear Fuel Structural Response when Subject to an End Impact Accident." In 2004 American Society of Mechanical Engineers, Pressure Vessels & Piping Division, 483, 207-214. New York, New York:American Society of Mechanical Engineers. PNNL-SA-41214.