Donna Post Guillen, Ph.D., P.E.
Principal Investigator/Technical Lead
Research Areas: Modeling and Simulation
Biography: Dr. Donna Post Guillen has over 35 years of research and engineering experience and has served as Principal Investigator/Technical Lead for numerous multidisciplinary projects encompassing waste heat recovery, combustion, heat exchangers, power conversion systems, nuclear reactor fuels and materials experiments, waste vitrification, and advanced manufacturing. Her core area of expertise is computational modeling of energy systems, materials and thermal fluid systems. She is experienced with X-ray and neutron beamline experiments, computational methods, tools and software for data analysis, visualization, application development, machine learning and informatics, numerical simulation, and design optimization. As Principal Investigator/Technical Lead for the DOE Nuclear Science User Facility Program, she has engaged in irradiation testing of new materials and performed thermal analysis for nuclear reactor experiments. She actively mentors students, serves in a leadership capacity as well as routinely chairs and organizes technical meetings for professional societies, provides subject matter reviews for proposals and technical manuscripts, has published over 100 papers and received three Best Paper awards, authored numerous technical reports and journal articles, and written/edited several books.
Ph.D., Engineering and Applied Science - Idaho State University
M.S., Aeronautics - California Institute of Technology
B.S., Mechanical Engineering - Rutgers University
Current activities:The Minerals, Metals and Materials Society (TMS)Energy Committee, Vice-Chair 2012-14, 2020-2022/Chair 2014-16/Past-Chair 2016-18; JOM Advisor 2018-present
American Nuclear Society - Book Publishing Committee 2006-present; Thermal Hydraulics Program Committee 2006-present, Thermal Hydraulics Executive Committee 2015-2017; Advances in Thermal Hydraulics 2014, Technical Program Chair
American Society of Mechanical Engineers -Thermal Hydraulics and CFD, Track Co-Chair 2013-2019, Track Chair 2020
ASME/ABET Mechanical Engineering Program Evaluator
National Science Foundation Expert Panel for Information Technology Research, May 2004
Waste Management Symposia (WM) – Sensors for Environmental Monitoring, Session Organizer
ASM International - Thermal Spray Society Recommended Practices Committee
American Welding Society (AWS) - Technical Committee Member C2 Thermal Spray
International Society of Automation (ISA)- SP99 Committee Member
American Institute of Chemical Engineers (AIChE) – Session Organizer
A Sensitivity Study of Sodium Heat Pipes for Microreactor Applications, International Topical Meeting on Advances in Thermal Hydraulics 2020 (ATH’20), Paris, France, March 31-April 3, 2020.
A Physics-Informed Machine Learning Model for the Analysis of Drywell Cooling Fan Failure, Progress in Nuclear Energy, in review.
Effect of Cold Cap Coverage and Emissivity on the Plenum Temperature in a Pilot-Scale Waste Vitrification Melter, International Journal of Applied Glass Science, DOI: 10.1111/ijag.15031.
Evolution of Chromium, Manganese and Iron Oxidation State during Conversion of Nuclear Waste Melter Feed to Molten Glass, Journal of Non-Crystalline Solids 531, March 2020.
Computationally Aided Design of a Small-Scale Waste-Glass Melter, 2020 Waste Management Symposia, Phoenix, AZ, March 8-12, 2020.
An Algorithm to Generate Synthetic 3D Microstructures from 2D Exemplars, JOM 72(1), p. 65-74, December 2019.
Development of a Non-Nuclear Microreactor Test Bed, Transactions of the American Nuclear Society 121, November 2019.
Investigation of Performance Enhancements for Air-Brayton/ORC Combined Cycles for Small (~2 MWe) Power Systems and Moderate Heat Source Temperature, JOM, Vol. 71, Issue 5, p. 1616-1622, May 2019.
Melter Modeling over a Range of Scales to Support Vitrification at the WTP, 2019 Waste Management Symposia, Phoenix, AZ, March 3-7, 2019.
Sensitivity Study of Forced Convection Bubbling in a Transparent Viscous Fluid as a Proxy for Molten Borosilicate Glass, Annals of Nuclear Energy, Vol. 125, p. 38-49, March 2019.
Particle Settling in a Simulated Melter Discharge Riser, Materials Letters, Vol. 236, p. 38-41, February 2019.
In Situ Tensile study of PM-HIP and Wrought 316L Stainless Steel and Inconel 625 Alloys with High Energy Diffraction Microscopy, Materials Science and Engineering A, September 2018.
Effect of Glass Viscosity on Foaming Behavior and Heat Transfer in a Laboratory-Scale Waste Glass Melter, International Topical Meeting on Advances in Thermal Hydraulics 2018 (ATH’18), Orlando, FL, November 11-15, 2018.
Evaluation of Organic Rankine Cycles in an Air-Brayton Combined Cycle for Microreactor Applications, International Topical Meeting on Advances in Thermal Hydraulics 2018 (ATH’18), Orlando, FL, November 11-15, 2018.
Development of a Validation Approach for an Integrated Waste Glass Melter Model, Nuclear Technology, Vol. 203(3), p. 244-260, September 2018.
An Eco-Friendly System for the Production of Value-Added Materials from Dairy Manure, JOM, Vol. 70, Issue 10, p 1946–1957, October 2018.
Response Surface Data for Sensitivity Study of Industrial Spray Injected Fluidized Bed Reactor, Data in Brief, September 2018.
Sensitivity Study of a Full-Scale Industrial Spray-Injected Fluidized Bed Reactor, Powder Technology, Vol. 334(1), p. 36-52, July 2018.
Crystallization behavior of iron‐ and boron‐containing nepheline (Na2O·Al2O3·2SiO2) based glasses: Implications on the chemical durability of high‐level nuclear waste glasses, Journal of the American Ceramic Society, Vol. 102(3), July 2018.
A Methodology to Reduce the Computational Cost of Transient Multiphysics Simulations for Waste Vitrification, Computers & Chemical Engineering, Vol. 115(12), p. 64-80, July 2018.
Validation Hierarchy for Waste Vitrification Models, Transactions of the American Nuclear Society, Vol. 118(1), June 2018, 1173-1176.
Numerical Comparison of Bubbling in a Waste Glass Melter, Annals of Nuclear Energy, Vol. 113, p. 380–392, 2018.
X-ray Tomography of Feed-to-Glass Transition of Simulated Borosilicate Waste Glasses, Journal of the American Ceramic Society, 100(9), p. 3883-3894, September 2017.
Neutron Irradiation of Nuclear Structural Materials Fabricated by Powder Metallurgy with Hot Isostatic Pressing, Transactions of the American Nuclear Society, Vol. 116, June 2017, p. 392-393.
Computational Fluid Dynamics Simulation of a Pilot-Scale Waste Glass Melter, Transactions of the American Nuclear Society, Vol. 115, November 2016.
Heat Transfer Model of a Small-Scale Waste Glass Melter with Cold Cap Layer, NUTHOS-11: The 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety, Gyeongju, Korea, October 9-13, 2016.
Framework and Algorithms for Illustrative Visualizations of Time-Varying Flows on Unstructured Meshes, Advances in Engineering Software, Vol. 97, p. 72-84, July 2016.
Measurement and Simulation of Thermal Conductivity of Hafnium-Aluminum Thermal Neutron Absorber Material, Metallurgical and Materials Transactions E: Materials for Energy Systems 3(3), 123-133, September 2016.
Three-Dimensional FIB/EBSD Characterization of Irradiated HfAl3-Al Composite, Top Fuel 2016, Boise, ID, September 11-15, 2016.
Computational Fluid Dynamics Modeling of Bubbling in a Viscous Fluid for Validation of Waste Glass Melter Modeling, International Topical Meeting on Advances in Thermal Hydraulics 2016 (ATH’16), New Orleans, LA, June 12-16, 2016.
Conversion of Nuclear Waste Melter Feed into Glass: Development and Application of the Cold Cap Mathematical Model, Society of Glass Technology Centenary Conference & European Society of Glass Science and Technology 2016 Conference, Sheffield, UK, September 4-8, 2016.
Measurement and Simulation of Thermal Conductivity of Hafnium-Aluminum Thermal Neutron Absorber Material, 2016 TMS Annual Meeting, Nashville, TN, February 14-18, 2016
Reduction of GHG Emissions through the Conversion of Dairy Waste to Value-Added Materials and Products, 2016 TMS Annual Meeting, Nashville, TN, February 14-18, 2016.
One-Dimensional Cold Cap Model for Melters with Bubblers, Journal of the American Ceramic Society 1-7, 2015.
Modeling the Vitrification of Hanford Tank Waste, Transactions of the American Nuclear Society, Vol. 112, June 2015.
Bubbling Behavior in a Waste Glass Melter, WIT Transactions on Engineering Sciences, Vol. 89, WIT Press, 2015.
Radiation Effects on the Thermophysical Properties of a New Neutron Absorbing Material, 2015 TMS Annual Meeting, Orlando, FL, March 15-19, 2015.
Development of a Metal Matrix Composite Material for Nuclear Reactor Applications, 2015 TMS Annual Meeting, Orlando, FL, March 15-19, 2015.
Thermal Predictions of the Cooling of Waste Glass Canisters, Transactions of the American Nuclear Society, Vol. 111, November 2014.
Thermal Evaluation of Alternate Shipping Capability for Irradiated Experiments, Nuclear Technology, Vol. 190, June 2015.
Procedure for 3D Microstructure Reconstruction of a Heterogeneous Metal Matrix Composite Material, 3D Materials Science 2014, Annecy, France, June 29 – July 2, 2014.
Microstructure of Aluminum Matrix in Composite Absorber Block Material, 2014 TMS Meeting, San Diego, CA, Feb. 16-20, 2014.
Thermal Evaluation of Alternate Shipping Capability for GTRI Experiments, International Topical Meeting on Advances in Thermal Hydraulics 2014, Reno, NV, June 16-20, 2014.
High conduction neutron absorber to simulate fast reactor environment in an existing test reactor, Journal of Radioanalytical and Nuclear Chemistry, Vol. 302, Issue 1, pp. 413-424, 2014.
Extensible Framework for Illustrative Visualization of Time-Varying Flows, 2013 Transactions of the American Nuclear Society, Vol. 108, Atlanta, GA, June 16-20, 2013.
Hazards of Thermal Expansion for Radiological Container Engulfed in Fire, 15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-15), Pisa, Italy, May 12-16, 2013.
Microhardness of Hafnium Aluminide Composite Material for Nuclear Reactor Applications, 2013 TMS Annual Meeting, San Antonio, TX, March 3-7, 2013.
Waste Heat Recovery from the Advanced Test Reactor Secondary Coolant Loop, Advances in Thermal Hydraulics Topical Meeting at the 2012 ANS Winter Meeting, San Diego, CA, November 11-15, 2012.
The Autoignition of Cyclopentane in an Ignition Quality Tester, Journal of Materials, Vol. 64, No. 8, August 2012.
Thermal Evaluation of Uranium Silicide Miniplates Irradiated at High Heat Flux, Nuclear Engineering and Design 250, September 2012, p. 237– 246.
Waste Heat Recovery Research at the Idaho National Laboratory, Texas Industries of the Future Technology Forum on Low Temperature Waste Heat Recovery in Chemical Plants and Refineries, Houston, TX, May 16, 2012.
Effect of Materials on the Autoignition of Cyclopentane, 2012 TMS Annual Meeting, Orlando, FL, March 11-15, 2012.
Development of a Computational Multiphase Flow Model for Fischer Tropsch Synthesis in a Slurry Bubble Column Reactor, Chemical Engineering Journal, Vol. 176-177, 2011, Pages 83-94.
Thermal Stability of Cyclopentane as an Organic Rankine Cycle Working Fluid, Energy & Fuels 25, September 2011, p. 4138 - 4144.
Thermal Predictions of New Composite Material during In-Pile Testing, 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH14-108, Toronto, Ontario, Canada, September 25-29, 2011.
Integrated Static and Flow-Through Capsule Assembly for Irradiation Testing, 2011 Transactions of the American Nuclear Society, June 2011.
Modeling of Biofuel Production Processes, 2011 Multiphase Flow Conference, Wessex Institute, Kos, Greece, June 15-17, 2011.
Development of a Direct Evaporator for the Organic Rankine Cycle, TMS 2011 Annual Meeting, San Diego, CA, February 27 - March 3, 2011.
Progress Towards Modeling of Fischer Tropsch Synthesis in a Slurry Bubble Column Reactor, 2010 AIChE Annual Meeting, Salt Lake City, UT, November 7-11, 2010.
Analysis of Developing Adiabatic Churn-Turbulent Gas/Liquid Two-Phase Flows, 7th International Conference on Multiphase Flow, ICMF 2010, Tampa, FL, May 30–June 4, 2010.
In-Pile Experiment of a New Material to Enable Fast Neutron Testing in ATR, 2010 International Congress on the Advances in Nuclear Power Plants (ICAPP '10), San Diego, CA, June 6-10, 2010.
Fabrication and Characterization of a Conduction Cooled Thermal Neutron Filter, 2010 International Congress on the Advances in Nuclear Power Plants (ICAPP '10), San Diego, CA, June 6-10, 2010.
Thermal Analysis of a Uranium Silicide Miniplate Experiment, Proceedings of the 13th International Nuclear Thermal Hydraulics Meeting (NURETH-13), Kanazawa, Japan, September 29-October 1, 2009.
Optimization of a Two-Fluid Hydrodynamic Model of Churn Turbulent Flow, Proceedings of ICONE17, 17th International Conference on Nuclear Engineering, Paper No. ICONE17-75113, Brussels, Belgium, July 12-16, 2009.
Development and Validation of a Multi-field Model of Churn-Turbulent Gas/Liquid Flows, Proceedings of ICONE17, Paper No. ICONE17-75210, 17th International Conference on Nuclear Engineering, Brussels, Belgium, July 12-16, 2009.
Incorporation of Reaction Kinetics into a Multiphase, Hydrodynamic Model of a Fischer Tropsch Slurry Bubble Column Reactor, AIChE Annual Meeting, Philadelphia, PA, November 16-20, 2008.
Kinetic Modeling of a Fischer-Tropsch Reaction over a Cobalt Catalyst in a Slurry Bubble Column Reactor for Incorporation into a Computational Multiphase Fluid Dynamics Model, International Pittsburgh Coal Conference 2008, Pittsburgh, PA, September 29 – October 2, 2008.
Thermal Hydraulic Effects of Fuel Plate Surface Roughness, Nuclear Engineering and Design, Vol. 238, Issue 9, p. 2480–2483, September 2008.
Experimental Capabilities and Hydrodynamic Data for Validation of Computational Hydrodynamics for Slurry Bubble Column Reactors, AIChE Annual Meeting, Salt Lake City, UT, November 1-4, 2007.
CFD Analysis of Turbulent Flow Phenomena in the Lower Plenum of a Prismatic Gas-Cooled Reactor, 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-12), Pittsburgh, PA, September 30-October 4, 2007.
Integrated Fischer Tropsch Modular Process Model, Proceedings of the 49th Annual Meeting of the Idaho Academy of Science, Idaho Falls, ID, April 19-21, 2007.
Computational Flow Predictions for the Lower Plenum of a High-Temperature, Gas-Cooled Reactor, 2006 Transactions of the American Nuclear Society, Vol. 95, November 2006, p. 827-828.
Effect of Grit-Blasting on Substrate Roughness and Coating Adhesion, Journal of Thermal Spray Technology, Vol. 15, No. 3, September 2006, p. 348-355.
Estimation of Critical Flow Velocity for Collapse of Gas Test Loop Booster Fuel Assembly, Proceedings of ICONE14, 14th International Conference on Nuclear Engineering, Miami, FL, July 17-20, 2006.
Restructuring RELAP5-3D for Next Generation Nuclear Plant Analysis, 2006 Transactions of the American Nuclear Society, Vol. 94, June 2006.
Specification of Surface Roughness for Hydraulic Flow Test Plates, Proceedings of the 6th International Surface Engineering Congress, Seattle, WA, May 15-17, 2006.
In-Flight Oxidation of Aluminum in the Twin-Wire Electric Arc Process, Journal of Thermal Spray Technology, Vol. 15, No. 1, March 2006, p. 63-71.
Process Control Systems in the Chemical Industry: Safety vs. Security, Process Safety Progress, Vol. 25, Issue 1, p. 40-43, March 2006.
Thermal Hydraulic Analysis of a Gas Test Loop System, 2005 Transactions of the American Nuclear Society, Vol. 93, November 2005.
Analysis of a Proposed Gas Test Loop Concept, 2005 RELAP5/ATHENA International Users Seminar, Jackson Hole, WY, September 7-9, 2005.
Oxidation Behavior of In-Flight Molten Aluminum Droplets in the Twin-Wire Electric Arc Thermal Spray Process, International Thermal Spray Conference, Basel, Switzerland, May 2-4, 2005.
Surface Preparation of Steel Substrates using Grit-Blasting, International Thermal Spray Conference, Basel, Switzerland, May 2-4, 2005.
A Survey of Department of Energy-Sponsored Geophysical Research for Shallow Waste Site Characterization, Vadose Zone Journal, Vol. 3, No. 1, February 2004.
Recommended Practice for the Handling and Usage of Gases in Thermal Spraying, International Thermal Spray Conference, Essen, Germany, March 6-8, 2002.
Safety Hazards Associated with Particles in the Thermal Spray Environment, International Thermal Spray Conference, Montreal, Quebec, Canada, May 2000.
A Methodology for Addressing Particulate Content in Department of Energy Spent Nuclear Fuel Containers, American Nuclear Society Annual Meeting, Boston, MA, June 1999.
A Combined Approach to Modeling Droplet Deformation and Solidification for Thermal Spray, ASM International Materials Solutions Conference, Chicago, IL, October 1998.
In-Flight Particle Measurements of Twin Wire Electric Arc Sprayed Aluminum, Journal of Thermal Spray Technology, Vol. 7, No. 1, March 1998, p. 58-63.
Investigation of the Feasibility of Using a Flexible Aerobrake for Mars Entry, Journal of the Astronautical Sciences, Volume 42, No. 2, April-June 1994.
Computational Fluid Dynamics Application to Flexible Aerobrake Design for Mars Entry, American Astronautical Society, Paper 91-424, Durango, CO, August 1991.
Energy Technology: Energy Technologies and Carbon Dioxide Management Symposium 2015, Proceedings of the TMS Annual Meeting & Exhibition, Co-Editor, 2012, 2015, 2016, 2017, 2018.
Nuclear Reactor Thermal Hydraulics, Ed., InTech Open Access Publisher, 2013.
CFD Applications for Predicting Flow Behavior in Advanced Gas Cooled Reactors, InTech Open Access Publisher, Computational Fluid Dynamics, ISBN 9789533071695, 2011.
Oxidation Behavior of Aluminum during Thermal Spray: Experimental Evidence and Analysis, VDM Verlag Publishers, 128 p., ISBN 9783639174755, 2009.
Guillen, Donna P., Porter, Douglas L., Swank, W. David, Erickson, Arnold W., 2014, "Neutron absorbers and methods of forming at least a portion of a neutron absorber," Patent 8,903,035, December 2, 2014.
Guillen, Donna P., Longhurst, Glen R., Porter, Douglas L., Parry, James R., 2012, "Methods for absorbing neutrons," Patent 8,229,054, July 24, 2012.
WM Symposia - Superior Paper, 2019.
TMS Light Metals Division, Distinguished Service Award, 2019.
TMS Energy Best Paper Award – Student Division, 2017.
TMS Light Metals Division Best Paper Award – Professional, 2014.
INL Exceptional Contributor - Advanced Test Reactor National Scientific User Facility, 2007.
INL Exceptional Contributor – Development of Integrated Modeling System, 2007.
American Society of Mechanical Engineers, ICONE-14 Certificate of Appreciation, 2006.
Performance Plus Awards, Bechtel BWXT Idaho, LLC, 2002, 2003.
Lockheed Martin Excellence Awards, 1995, 1998, 1999.
Special Recognition for Innovation in Development of the Integrated Spent Nuclear Fuel Database System, EG&G Idaho, Inc., 1994.
Independent Research and Development Program, Honor Roll Award, TRW Inc.