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Harold Adkins

Harold Adkins

Pacific Northwest National Laboratory
PO Box 999
Richland, WA 99352

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

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.
  • 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.

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 Cuclear Power Station ISFSI. PNNL-22552; FCRD-UFD-2013-000297. Richland, WA: Pacific Northwest National Laboratory.
  • 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.
  • 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.
  • 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.
  • 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.
  • 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.

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.
  • 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.
  • 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.
  • 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.

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.
  • 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.
  • 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.
  • 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

  • Geelhood K.J., W.G. Luscher, D.J. Senor, M.E. Cunningham, D.D. Lanning, and H.E. Adkins. 2009. Predictive Bias and Sensitivity in NRC Fuel Performance Codes. NUREG/CR-7001; PNNL-17644. Richland, WA: Pacific Northwest National Laboratory.
  • 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.
  • 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.
  • 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.

2007

  • Adkins H.E., B.J. Koeppel, and J.M. Cuta. 2007. Spent Fuel Transportation Cask Response to the Caldecott Tunnel Fire Scenario. NUREG/CR-6894 Rev1; PNNL-15346. Richland, WA: Pacific Northwest National Laboratory.
  • 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.

2006

  • Adkins H.E., J.M. Cuta, B.J. Koeppel, A.D. Guzman, and C.S. Bajwa. 2006. Spent Fuel Transportation Package Response to the Baltimore Tunnel Fire Scenario. NUREG-CR-6886 Rev.1; PNNL-15313. Richland, WA: Pacific Northwest National Laboratory.

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.

Experimental and Computational Engineering

Additional Information