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Energy and Environment Directorate

Harold Adkins

Harold Adkins

Pacific Northwest National Laboratory
PO Box 999
Richland, WA 99352
(509) 372-6629

Biography

Current assignments include performing advanced 2-D axisymmetric and 3-D structural evaluations and providing engineering support to development programs for large caliber concept munitions, die casting technologies, and non-lethal acoustic technologies. Evaluations include projectiles and accompanying cartridge components under static, quasi-static, in-bore acceleration, muzzle exit deceleration and discard loading conditions as well as performing structural design optimizations and parametric sensitivity to reduce parasitic and total cartridge mass. Current assignments also include performing advanced 2-D axisymmetric and 3-D thermal analyses involving intricate mass, convective, and radiative transfer regimes for the safety verification of commercial spent nuclear fuel transport, transfer, and storage systems governed by the NRC. Solution methods included large-scale Finite Element Analyses (FEA), large-scale Finite Difference Analyses (FD), a combination of the two, or a combination of empirical and traditional hand calculation methods.

Education and Credentials

  • M.S., Mechanical Engineering, University of Wyoming, Laramie, WY, 1997
  • B.S., Mechanical Engineering, University of Wyoming, Laramie, WY, 1991

PNNL Publications

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 Probablistic Safety Assessment and Management. PNNL-SA-172477.
  • Jenks J.W., C.L. Painter, H.E. Adkins, D.J. Sunderland, R.A. Schwarz, S.R. Suffield, and B.E. Bernacki, et al. 2022. A Very High Temperature Lead Cooled Microreactor Concept using Advanced Materials and Thermophotovoltaics Direct Energy Conversion Technology. PNNL-32953. Richland, WA: Pacific Northwest National Laboratory. A Very High Temperature Lead Cooled Microreactor Concept using Advanced Materials and Thermophotovoltaics Direct Energy Conversion Technology

2021

  • Coles G.A., S.M. Short, S.J. Maheras, and H.E. Adkins. 2021. Proposed Risk-Informed Regulatory Framework for Approval of Microreactor Transportation Packages. PNNL-31867. Richland, WA: Pacific Northwest National Laboratory.
  • 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
  • Maheras S.J., G.A. Coles, J.R. Phillips, C.A. Condon, S.M. Short, H.E. Adkins, and P.P. Lowry, et al. 2021. Plan for Development and Application of Risk Assessment Approach for Transportation Package Approval of an MNPP for Domestic Highway Shipment. PNNL-33524. Richland, WA: Pacific Northwest National Laboratory. Plan for Development and Application of Risk Assessment Approach for Transportation Package Approval of an MNPP for Domestic Highway Shipment

2020

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

  • 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.
  • 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.
  • Sanborn S.E., B.J. Koeppel, N.A. Klymyshyn, H.E. Adkins, and K.J. Geelhood. 2014. "Assembly Level Modeling and Transportation Damage Prediction of Used Nuclear Fuel (UNF) Cladding." In Annual Wate Management Symposium (WM 2014), March 2-6, 2014, Phoenix, Arizona, 7, 5994-6008. Tucson, Arizona:Waste Management Symposia, Inc. PNNL-SA-100207.

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.
  • 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, and B.D. Hanson. 2013. "ASSESSING MATERIAL DEGRADATION EFFECTS ON LONG TERM STORAGE STRUCTURAL ANALYSES." In Proceedings of the 14th International High-Level Radioactive Waste Management Conference (IHLRWMC 2013), April 28-May 2, 2013, Albuquerque, NM, 247-252. La Grange Park, Illinois:American Nuclear Society. PNNL-SA-92732.
  • 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

2012

  • Bajwa C., E.P. Easton, H.E. Adkins, J.M. Cuta, N.A. Klymyshyn, and S.R. Suffield. 2012. "The MacArthur Maze Fire and Roadway Collapse: Consequences for SNF Transportation - 12476." In Proceedings of the Annual Waste Management Symposium (WM 2012): Improving the Future in Waste Management, February 26-March 1, 2012, Phoenix, AZ, 5, 3859-3872. Tucson, Arizona:WM Symposia, Inc. PNNL-SA-84729.
  • 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, 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 Managemetn Symposium (WM 2012): Improving the Future in Waste Management, February 26-March 1, 2012, Phoenix, Arizona, Paper No. 12518. Tuscson, 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.

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, Aizona, 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.
  • 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.

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.

Energy and Environment

Core Research Areas

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