Researcher

Rebecca Smith

Engineer Principal Investigator

Research Areas:
Materials Characterization

Biography:

Rebecca E. Smith is a principal investigator and engineer at Idaho National Laboratory. She has been responsible for assessing material interactions for nuclear fuel and its containment and analyzing handling and environmental conditions to ensure safe operations. She has written specifications and reviewed vendor data to ensure compliance with design, and installed equipment and developed test procedures for use during start up. She has created detailed test plans and conducted research to address emerging technical needs, from drying and conditioning corroded fuel materials, to analysis of oxidation and graphite performance in support of new reactor designs. She holds a bachelor’s in chemical engineering with a minor in psychology from Massachusetts Institute of Technology.

Education:

B.S., Chemical Engineering - Massachusetts Institute of Technology

Publications:

I. Van Rooyen, D. Scates, R. Smith, K. Jamison, E. Luther, A. Crawford, T. Lister, and H. Hartman, “PLN-4807 Transient Reactor Test Facility Fuel Conversion Qualification Plan,” INL/MIS-15-36941, Rev. 0, October 2015.

W. Windes, R Smith, and M. Carroll, “Effects of Oxidation on Oxidation-Resistant Graphite,” INL/EXT-15-35050, Rev. 0, April 2015.

R. Smith, “SPC-1824 Pyrolytic Graphite Insulator Material for TREAT LEU Fuel Assemblies,” Rev. 0, January 2015.

W. Windes, G. Strydom, R. Smith, and J. Kane, “Role of Nuclear Grade Graphite in Controlling Oxidation in Modular HTGRs, INL/EXT-14-31720, Rev. 0, November 2014.

R.E. Smith, “Phase 1 Final Transmittal for WFO No. 13819”, INL/LTD-14-32810, September 2014.

W. Windes and R. Smith, “Oxidation-Resistant Graphite Studies,” INL/EXT-14-32513, Rev. 0, July 2014.

R. Smith, W. Windes, and N. Woolstenhulme, “Review of Historical Information Pertaining to TREAT LEU Conversion Design Options,” INL/LTD-13-30320, Rev. 0, December 2013.

R.E. Smith, “Operational Assessment of the Can-In-Can Concept,” INL/MIS-12-25842, Rev. 2, July 2012.

R.E. Smith, “Annotated Bibliography for Drying Nuclear Fuel,” INL/EXT-11-23561, Rev. 0, September 2011.

R.E. Smith, “Status of Graphite Oxidation Work,” INL/EXT-10-18880, Rev. 0, May 2010.

R.E. Smith, “DOE SNF Material Interaction Potentials during an Intrusive Igneous Event at Yucca Mountain,” DOE/SNF/REP-108, August 2007.

R.E. Smith, “TRIGA Fuel Summary Report,” ICP/INT-05-00817, Rev. 0, March 2005.

R.E. (Lords) Smith, “Drying Characteristics of Thorium Fuel Corrosion Products,” Journal of Nuclear Materials, NUMA41496, Vol. 328, No. 2-3, pp. 215-224, July 1, 2004.

M.A. Ebner and R. E. Smith, “EDF-4262 Consequences of Rover Parka Fuel Reaction with Water,” October 2003.

R.E. Smith, “PLN-929 INEEL Spent Nuclear Fuel Characterization Plan,” September 2003.

R.E. Smith, “EDF-3479 Evaluation of Potential for Denitrator Product Pyrophoricity,” February 2003.

R.E. Lords, “Literature Review of the Drying Characteristics of Thorium Spent Fuel Corrosion Products,” April 2002.

R. Finch, R.E. Lords, ed., S. Morton, ed., “ANL X-ray Powder Diffraction Analysis of AECL ‘Sludge’ Samples 18146 and 18147,” March 2002.

J. Henscheid, S. Sam Kim, T. Larson, R. Lords, D. Marts, T. Criddle, and P. Winston, “Feasibility Study on Appropriate Technologies for Storage and Disposition of Spent Nuclear Fuel from Soviet-Designed Research Reactors,” INL/MIS-11-20777, February 2002.

R.E. Lords and M.A. Ebner, “EDF-3138 Evaluation of Flammability Potential During Drying of Polymeric Materials at 100ºC,” January 2002.

R.E. Lords, “Survey of Measurement Techniques to Determine Dryness of Dried Spent Nuclear Fuel,” December 2001.

R.E. Lords, “Baseline Thermal Tests on Polymeric Mounting Materials,” October 2001.

R.E. Lords and R.K. McCardell, “Technical Basis for Drying Damaged Spent Nuclear Fuel,” October 2001.

R.E. Lords and M.A. Ebner, “EDF-2575 An Evaluation of Operating Options for the Drying of Polymeric Materials from MTR,” May 2001.

R.E. Lords and G.L. Olson, “EDF-1852 Mass Loss Experiments for Potting Compounds,” April 2001.

R.E. Lords, “INEEL Process Drying Report,” September 2000.

R.E. Lords and G.L. Olson, “Characteristics and Potential Hazards of Mounting Compounds Contained in the Fuel Stored In and Near the MTR Canal,” September 2000.

R.E. Lords, M.A. Ebner, and C. Rae, “EDF-1500 Pyrolysis of DER 332 Epoxy During Drying,” July 2000.

J.C. Crepeau, S. Reese, H.M. McIlroy, and R.E. Lords, “Drying of Mock Spent Nuclear Fuel Elements,” Drying Technology, Vol. 16, No. 3-5, pp. 545-560, 1998.

R.E. Lords, D.L. Hale, J.W. Sterbentz, W.E. Windes, K.L. Young, and M.A. Ebner, “University of Illinois TRIGA Fuel Summary Report,” September 1996.

R.E. Lords, “SNAP and AI Fuel Summary Report,” August 1994.

Presentations:

R.E. Lords and D.W. Akers, “Managing Epoxy-Bearing Spent Nuclear Fuel Samples,” 2000, presented by Lords at the American Nuclear Society Topical Meeting in San Diego, CA.

R.E. Lords, “Five Years of INEEL Spent Nuclear Fuel Drying Experience,” 1998 presented by Lords at the American Nuclear Society Topical Meeting in Charleston, SC.

R.E. Lords, W.E. Windes, J.C. Crepeau, and R.W. Sidwell, “Drying Studies of Simulated DOE Aluminum Plate Fuels,” 1996, presented by Windes at the American Nuclear Society Topical Meeting in Reno, NV.

J.C. Lopez, R.E. Lords, A.P. Pinto, “Integrated Conditioning Process for Spent Graphite Fuels,” March 1994, presented by Lords at the Waste Management ‘94 Symposia in Tucson, AZ.

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