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Sarah Suffield

Pacific Northwest National Laboratory
PO Box 999
Richland, WA 99352

PNNL Publications

2018

  • Bao J., T. Zhou, M. Huang, Z. Hou, W.A. Perkins, S.F. Harding, and P. Titzler, et al. 2018. "Modulating factors of hydrologic exchanges in a large-scale river reach: Insights from three-dimensional computational fluid dynamics simulations." Hydrological Processes 32, no. 23:3446-3463. PNNL-SA-123673. doi:10.1002/hyp.13266

2017

  • Peterson R.A., S.K. Fiskum, S.R. Suffield, R.C. Daniel, P.A. Gauglitz, and B.E. Wells. 2017. Simulant Basis for the Standard High Solids Vessel Design. PNNL-24476 Rev 1; WTP-RPT-241 Rev 1. Richland, WA: Pacific Northwest National Laboratory. Simulant Basis for the Standard High Solids Vessel Design

2016

  • Kabilan S., S.R. Suffield, K.P. Recknagle, R.E. Jacob, D.R. Einstein, A.P. Kuprat, and J.P. Carson, et al. 2016. "Computational Fluid Dynamics Modeling of Bacillus anthracis Spore Deposition in Rabbit and Human Respiratory Airways." Journal of Aerosol Science 99. PNNL-SA-108616. doi:10.1016/j.jaerosci.2016.01.011
  • Meyer R.M., S.R. Suffield, E.H. Hirt, J.D. Suter, J.P. Lareau, J. Zhuge, and H. Qiao, et al. 2016. Nondestructive Examination Guidance for Dry Storage Casks. PNNL-24412 Rev. 1. Richland, WA: Pacific Northwest National Laboratory. Nondestructive Examination Guidance for Dry Storage Casks
  • Peterson R.A., S.K. Fiskum, S.R. Suffield, R.C. Daniel, P.A. Gauglitz, and B.E. Wells. 2016. Simulant Basis for the Standard High Solids Vessel Design. PNNL-24476 Rev 0;WTP-RPT-241, Rev 0. Richland, WA: Pacific Northwest National Laboratory. Simulant Basis for the Standard High Solids Vessel Design

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.
  • 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
  • Recknagle K.P., J.M. Barnett, and S.R. Suffield. 2013. Modeling the Air Flow in the 3410 Building Filtered Exhaust Stack System. PNNL-22185. Richland, WA: Pacific Northwest National Laboratory. Modeling the Air Flow in the 3410 Building Filtered Exhaust Stack System

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
  • 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, Aizona, Paper No. 11392. Tucson, Arizona:WM Symposia. PNNL-SA-76810.

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.

Experimental and Computational Engineering

Additional Information