OREGON STATE UNIVERSITY
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Tucker, J., Wei, Y., Marcum, W.R., Murkute, P., Gibbons, B., Isgor, O., “Characterization of Oxide Growth of Aluminum Alloy 6061 for Nuclear Research and Test Reactors”, Metallurgical and Materials Transactions A. 2019. https://doi.org/10.1007/s11661-019-05256-3.
Goodrich, S.S., Marcum, W.R., “Natural Convection Heat Transfer and Boundary Layer Transition for Vertical Heated Cylinders”, Experimental Thermal and Fluid Science, Volume 105, pp. 367-380.
Zabriskie, A., Shunert, S., Schwen, D., Ortensi, J., Baker, B., Wang, Y., DeHart, M., Marcum, W., “A Coupled Multi-scale Approach to TREAT LEU Modeling Using a Binary-Collision Monte-Carlo Informed Heat Source”, Nuclear Science & Engineering. Volume 193, Issue 4, pp. 368-387
Balderrama, S.A., Mignot, G.P., Marcum, W.R., Woolstenhulme, N.E., “CFD Modeling of the Density Evolution Inside of the HENRI System”, American Nuclear Society Winter Meeting, Washington D.C., USA, 2019.
Lilley, B., Palmer, T., LaBrier, D., Higgins, A., Marcum W.R., “Neutronic Analysis of a Liquid Metal Fast Reactor Experiment for the Large-I Position of the Advanced Test Reactor”, International Fuel Cycle Conference – Top Fuel 2019, Westin Seattle, WA, September 22-26, 2019.
LaBrier, D.L., Schulthess, J., Marcum W.R., Meyer, M.K., “Improving the Fuel Qualification Process through the Use of Microscale Samples for Describing Bulk Material Properties”, International Fuel Cycle Conference – Top Fuel 2019, Westin Seattle, WA, September 22-26, 2019.
Higgins, A., LaBrier, D., Marcum, W.R., “Thermal Hydraulic Design of an In-Pile Experimental Loop for Fast Test Reactor Conditions”, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Portland, OR, USA, August 18-22, 2019. pp. 3865-3878.
Mignot, G., Warren, A., Balderrama, S., Marcum, W.R., Woolstenhulme, N., “Experiments on Helium-3 Negative Reactivity Insertion – HENRI – Prototype”, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Portland, OR, USA, August 18-22, 2019. pp. 1772-1783.
Yan, Y., Brown, E.G., Marcum, W.R., “Analytical Solution to a one-dimensional two-region heat conduction problem with time dependent heat input”, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Portland, OR, USA, August 18-22, 2019. pp. 4831-4840.
Yan, Y., Brown, E.G., Marcum, W.R., “Modeling Path of the Heterogeneous Spontaneous Nucleation – A New Driven Mechanism of Power Transient CHF”, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Portland, OR, USA, August 18-22, 2019. pp. 1882-1892.
Weiss, A.W., Marcum, W.R., Jones, W.F., Phillips, A.M., Holschuh, T.V., Howard, T.K., “Application of Strain Gages in a Highly Advective Environment for Measurement of Fluid-Structure Interactions”, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Portland, OR, USA, August 18-22, 2019. pp. 4912-4925.
Brown, E.G., Yan, Y., Marcum, W.R., “A Novel Method for Predicting Power Transient CHF via the Heterogeneous Spontaneous Nucleation Trigger Mechanism”, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Portland, OR, USA, August 18-22, 2019. pp. 6117-6129.
Wieland, I., Duenas, A.M., Marcum, W.R., Wu, Q., “Investigation of the Mechanisms which Govern Bubble Geometry in the Spherical Cap Regime Through the Application of Particle Image Velocimetry”, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Portland, OR, USA, August 18-22, 2019. pp. 5204-5217.
Chen, T.S., Marcum, W.R., “A New Approach of Studying Transient Boiling Based on the CHF Simulation and Past Experimental Studies”, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Portland, OR, USA, August 18-22, 2019. pp. 3792-3805.
Chen, T.S., Marcum, W.R., “A New Hypothesis of Transient Boiling Based on the CFD Simulation and Past Experimental Studies”, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Portland, OR, USA, August 18-22, 2019. pp. 3806-3819.
Marcum, W.R., Gjemso, J., “A CFD Study on the Hydrodynamics for Tandem Plate Configurations under Turbulent Flow”, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Portland, OR, USA, August 18-22, 2019. pp. 3195-3205.
Duenas, A.M., Wieland, I., Marcum, W.R., Wu, Q., “Investigation of Drag and Virtual Mass Coefficients for Rising Ellipsoidal Bubbles”, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Portland, OR, USA, August 18-22, 2019. pp. 2992-3004.
LaBrier, D.P., Yan, Y., Brown, E.G., Marcum, W.R., “Developing Separate Effects Transient Test Experiments Using an out-of-Pile Flowing Water Loop”, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Portland, OR, USA, August 18-22, 2019. pp. 4983-4993.
Latimer, G.D., Marcum, W.R., Jones, W.F., “Dispersion of Surrogate LWR Fuel Experiments under LOCA Conditions”, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Portland, OR, USA, August 18-22, 2019. pp. 4050-4062.
Balderrama, S.A., Mignot, G.P., Marcum, W.R., Woolstenhulme, N.E., “Design and CFD Modeling of the Gas Injection System for the Out-of-Pile HENRI Facility”, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Portland, OR, USA, August 18-22, 2019. pp. 2164-2176.
Nixon, C.A., Marcum, W.R., “Dynamics of a Solitary Wire-Wrapped Pin in Axial Flow: A Theoretical Model”, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Portland, OR, USA, August 18-22, 2019. pp. 5639-5651.
Nixon, C.A., Marcum, W.R., Weiss, A.W., Steer, K.M., Jackson, R.B., Martin, M.G., Yeager, C., “Dynamics of a Solitary Wire-Wrapped Pin in Axial Flow: A Theoretical Model”, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Portland, OR, USA, August 18-22, 2019. pp. 4926-4933.
Nixon, C.A., Marcum, W.R., Steer, K.M., Jackson, B.R., “A New Method for Experimentally Quantifying Dynamic Deflection of a Cylindrical Structure”, Experimental Mechanics. Volume 58, Issue 9, pp. 1351-1369, August, 2018.
Latimer, G.D., Marcum, W.R., Howard, T.K., Jones, W.F., Phillips, A.M. Woolstenhulme, N., Liu, S., Weiss, A.W., Campbell, J., Moussaoui, M., Jensen, C., “Experimental Vibration Analysis of an Externally Excited Nuclear Reactor Experiment Design”, Nuclear Engineering and Design, Volume 335, pp. 1-17, August, 2018.
Holschuh, T.V., Marcum, W.R., “Modified Fuchs-Nordheim Model for use in Reactor Pulse Experiments”, Annals of Nuclear Energy, Volume 116, pp. 314-318, June 2018.
Jones, W.F., Marcum, W.R., Weiss, A.W., Jensen, C.B., Hawkes, G.L., Murray, P.E., Crawford, D.S., Herter, J.W., Kennedy, J.C., Woolstenhulme, N.E., Wiest, J.D., Chapman, D.B., Howard, T.K., Latimer, G.D., “Reducing Uncertainty in Hydrodynamic Modeling of ATR Experiments via Flow Testing, Validation, and Optimization” Nuclear Technology, Special Issue. Volume 201, Issue 3, pp. 286-303, January 2018.
, C.J., Kennedy, J.C., Phillips, A.M., Marcum, W.R., Weiss, A.W., “Generic Test Plate Assembly Flow Testing Update”, 39th International Meeting on Reduced Enrichment for Research and Test Reactors, Edinburgh, Scotland, UK, November 4-7, 2018.
Latimer, G.D., Marcum, W.R., Jones, W.F., “Single Rod and 5x5 Rod Bundle Blowdown Experiments on the Dispersion of Surrogate Fuel”, International Topical Meeting on Advances in Thermal Hydraulics – 2018, Orlando, FL, USA, November 11-15, 2018. pp. 777-788.
Howard, T.K., Marcum, W.R., “On Scaling Theory of Vortex Shedding of Tandem Plates”, International Topical Meeting on Advances in Thermal Hydraulics – 2018, Orlando, FL, USA, November 11-15, 2018. pp. 586-599.
Nixon, C.A., Marcum, W.R., Steer, K.M., Jackson, R.B., “On the Fluid Structure Interactions of a Wire-Wrapped Pin Bundle”, International Topical Meeting on Advances in Thermal Hydraulics – 2018, Orlando, FL, USA, November 11-15, 2018. pp. 493-504.
Mignot, G.P., Balderrama, S.A., Woolstenhulme, N.E., Marcum, W.R., “Design of Helium 3 Negative Reactivity Insertion Device for the TREAT Reactor”, International Topical Meeting on Advances in Thermal Hydraulics – 2018, Orlando, FL, USA, November 11-15, 2018. pp. 892-903.
LaBrier, D.P., Stewart, R.H., Higgins, A., Lilley, B., Palmer, T.S., Marcum, W.R., “Design of an In-Pile Experimental Loop for Fast Test Reactor Conditions”, American Nuclear Society Winter Meeting, Orlando, FL, USA, November 11-15, 2018. Vol. 119. pp. 1271-1274.
Brown, E., Yan, Y., LaBrier, D., Marcum, W., “Design of a Flow Loop for Visualization and Characterization of Power Transient Critical Heat Flux”, American Nuclear Society Winter Meeting, Orlando, FL, USA, November 11-15, 2018. Vol. 119. pp. 488-491.
LaBrier, D.L., Marcum, W.R., Nylander, J., “Development of a Novel Resistive Heater for Performing Simulated Nuclear Fuel Experiments”, American Nuclear Society Annual Meeting, Philadelphia PA, USA, June 17-21, 2018. Vol. 118. pp. 1113-1116.
LaBrier, D.L., Marcum, W.R., Weiss, A.W., Mignot, G.P., Brown, E., Yan, Y., Moussaoui, M., Chen T.W., “On the Performance of the Transient Reactor Test Loop (TRTL)”, American Nuclear Society Annual Meeting, Philadelphia PA, USA, June 17-21, 2018. Vol. 118. pp. 1130-1133.
Mignot, G.P., Marcum, W.R., O’Brien, S., “A New High Pressure Pump Test Loop”, American Nuclear Society Annual Meeting, Philadelphia PA, USA, June 17-21, 2018. Vol. 118. pp. 1127-1129.
Zabriskie A.X., Baker, B., Ortensi, J., DeHart, M.K., Marcum, W.R., “Self-Controlling Transient Pulse Simulation Method Exhibiting Time-Lag Phenomenon Using Mammoth”, The Physics of Reactors Conference, PHYSOR 2018, Cancun, Mexico, April 22-26, 2018 pp 1-11.
Holschuh, T.V., Marcum, W.R., Palmer, T.S., “One-Group Analytical Solution to Two-Region Reactor Kinetic Model”, Annals of Nuclear Energy. Volume 99, pp 199-205, January 2017.
Jones, W.F., Marcum, W.R., Weiss, A.W., “Generic Test Plate Assembly Flow Testing Update”, International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR 2017), Chicago, United States, S10-P12, pp 1-10, November 12-15, 2017.
Latimer, G.D., Marcum, W.R., Jones, W.F., “Advection and Diffusion Calculations Supporting Fuel Fragmentation, Relocation, and Dispersion Experiments”, American Nuclear Society Winter Meeting, Washington D.C., USA, 2017.
Latimer, G.D., Marcum, W.R., Jones, W.F., “Plume Progression of a Ruptured Fuel Element in a Representative 5x5 PWR Fuel Assembly”, American Nuclear Society Winter Meeting, Washington D.C., USA, 2017.
Howard, T.K., Marcum, W.R., Jones, W.F., “An Investigation of the Dominate Plate Modes from End Excitation”, American Nuclear Society Winter Meeting, Washington D.C., USA, 2017.
Lee, Y.H, Blandford, E., Brown, N., Marcum, W.R., Walker, S., Hewitt, G., Issa, R., Jensen, C., Strumpell, J., Rebak, R., “A NEUP Example of US-UK Collaboration: An Experimental and Analytical Investigation into Critical Heat Flux Implications for Accidental Tolerant Fuel Concepts”, America Nuclear Society Winter Meeting, Washington D.C., USA, 2017.
Nixon, C.A., Marcum, W.R., Steer, K.M., Jackson, R.B., Weiss, A.W., “Measuring the Dynamic Response of a Wire-Wrapped Pin in Flow”, 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Xi’an, China, September 3-8, 2017.
Howard, T.K., Jones, W.F., Marcum, W.R., “A Computational Approach and Experimental Validation for the Assessment of Added Mass for Fuel Plates”, 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Xi’an, China, September 3-8, 2017. (academic advisory)
Marcum, W.R., Phillips, A.M., Jones, W.F., Weiss, A.W., Howard, T.K., “Early Observations on the Experimental Study of Fluid-Structure-Interactions While Testing Plate Type Fuel”, 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Xi’an, China, September 3-8, 2017.
Goodrich, S., Marcum, W.R., “Natural Convection Heat Transfer and Boundary Layer Transition from Vertical Heated Cylinders”, 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Xi’an, China, September 3-8, 2017.
Goodrich, S., Marcum, W.R., “Natural Convection Heat Transfer and Boundary Layer Transition for Vertical Heated Cylinders” American Society of Mechanical Engineers 2017 Summer Heat Transfer Conference, Bellevue, Washington, United States. July 9-12, 2017.
LaBrier, D.P., Marcum, W.R., “Methodology of Experiment Design for Transient Critical Heat Flux Model Development”, 2017 American Nuclear Society Annual Meeting, San Francisco, California, United States, June 11-15, 2017. Vol. 116, pp. 1397-1400.
Brown, E.G., Marcum, W.R., Jensen, C.B., “Modeling the Transient Reactor Test Loop in TRACE for PWR Critical Heat Flux Benchmarking”, 2017 American Nuclear Society Annual Meeting, San Francisco, California, United States, June 11-15, 2017. Vol. 116, pp. 1455-1457.
Hawkes, G., Marcum, W.R., Weiss, A.W., *Howard, T.K., “Flow Testing and Analysis of the FSP-1 Experiment”, 2017 American Society of Mechanical Engineers Power and Energy Conference and Exhibition, Charlotte, North Carolina, United States. June 26-30, 2017. pp. 1-9.
Holschuh, T.V., Marcum, W.R., Palmer, T.S., “One-Group Analytical Solution to Two-Region Reactor Kinetic Model”, Annals of Nuclear Energy. Volume 99, pp 199-205, September 2016.
Marcum, W.R., Harmon, P.L., “Characterizing Fluid Structure Interactions of a Helical Coil in Cross Flow”, Journal of Fluids and Structures. Volume 65, pp. 355-380, June 2016.
Marcum, W.R., Wachs, D.M., Robinson, A.B., Lillo, M.A., “Aluminum Cladding Oxidation of In-Pile Fueled Experiments”, Journal of Nuclear Materials, Volume 471, pp 136-148, April 2016.
Jones, W.F., Jensen, C.B., Crawford, D.S., Marcum, W.R., Weiss, A.W., Howard, T.K., Latimer, G.D., “USHPRR Fuel Development Flow Testing Overview” International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR 2016), Antwerp, Belgium, pp. 1-10, October 23-27, 2016.
Howard, T.K., Marcum, W.R., “An Approach to Assessment of Added Mass for a Plate in a Channel”, 2016 American Nuclear Society Winter Meeting, Las Vegas, Nevada, United States, November 6-10, 2016. Vol. 115, pp. 1546-1549.
Nixon, C.A., Marcum, W.R., Steer, K.M., Widdle, R.D., Jackson, R.B., Weiss, A., “The Dynamic Response of a Wire-Wrapped Pin – A New Experimental Method”, 2016 American Nuclear Society Winter Meeting, Las Vegas, Nevada, United States, November 6-10, 2016. Vol. 115, pp. 1692-1695.
Latimer, G.D., Marcum, W.R., Howard, T.K., Jones, W.F., Phillips, A.M., Woolstenhulme, N., Weiss, A.W., “Vibration Analysis of Advanced Test Reactor Mini-Plate Hydraulic Tests in the OSU HMFTF”, 2016 American Nuclear Society Winter Meeting, Las Vegas, Nevada, United States, November 6-10, 2016. Vol. 115, pp. 1542-1545.
Latimer, G.D., Marcum, W.R., Jones, W.F., “Advanced Test Reactor Mini-Plate Hydraulic Testing”, 2016 American Nuclear Society Annual Meeting, New Orleans, Louisiana, United States, June 12-16, 2016. Vol. 114, pp. 856-859.
Howard, T.K., Marcum, W.R., Jones, W.F., “Scaling Analysis of Vortex Shedding Between Inline Plates”, 2016 American Nuclear Society Annual Meeting, New Orleans, Louisiana, United States, June 12-16, 2016. Vol. 114, pp. 860-863.
Howard, T.K., Marcum, W.R., Latimer, G.D., Weiss, A., Jones, W.F., Phillips, A.M., Woolstenhulme, N., Holdaway, Campbell, J., “Accelerometers in Flow Fields: A structural Analysis of the Chopped Dummy In-Pile Tube”, Advances in Thermal Hydraulics, 2016 American Nuclear Society Annual Conference, New Orleans, Louisiana, United States, June 12-16, 2016. pp. 1-14.
Holschuh, T.V., Marcum, W.R., Chichester, D.L., Watson, S.M., Morrell, S.R., “Using Cherenkov Light to Quantify Reactor Kinetics Parameters and Infer Fissile Material Inventory for Nuclear Nonproliferation”, The Physics of Reactors Conference, PHYSOR 2016, Sun Valley, Idaho, United States, May 1-5, 2016. pp 1-10.
Marcum, W.R., Brigantic, A.J., “Applying Uncertainty and Sensitivity on Thermal Hydraulic Subchannel Analysis for the Multi-Application Small Light Water Reactor”, Nuclear Engineering and Design, Volume 293, pp 272-291, November 2015.
Howard, T.K., Marcum, W.R., Jones, W.F., “A Novel Approach to Modeling Fluid Structure Interactions,” Nuclear Engineering and Design, Volume 293, pp 1-15, November 2015.
Marcum, W.R., Holschuh T.V., Howard, T.K. “On the Steady Mechanical Response of a Heterogeneous Fuel Plate”, Nuclear Technology, Invited Article, Special Issue, Volume 190, Number 2, pp. 359-375, June 2015.
Marcum, W.R., Byfield, P.Y., Reese, S.R., “A New Molybdenum Production Element for Implementation in TRIGA Reactors – Thermal Hydraulic Characterization,” Nuclear Science and Engineering, Volume 180, Number 2, pp 123-140, June 2015.
Marcum, W.R., Cadell, S., Ward, C., “The Effect of Jet Location and Duty Cycle on the Fluid Mechanics of an Unconfined Free Jet and its Heat Transfer on an Impinging Unconfined Air Jet”, International Journal of Heat and Mass Transfer, Volume 88, pp 470-480, May 2015.
Lyons, J.A., Marcum, W.R., Morrell, S., DeHart, M., “Reactor Physics Scoping and Characterization Study on Implementation of TRIGA® Fuel in the Advanced Test Reactor,” Nuclear Technology, Volume 189, pp. 202-217, February 2015.
Harmon, P.L., Marcum, W.R., “Comprehensive Characterization of a Helix Motion due to Flow Induced Vibration”, 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Chicago, Illinois, United States, August 30-September 4, 2015. pp. 7701-7713.
Brigantic, A., Marcum, W.R., “Applying Uncertainty and Sensitivity on Thermal Hydraulic Subchannel Analysis for the Multi-Application Small Light Water Reactor”, 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Chicago, Illinois, United States, August 30-September 4, 2015. pp. 5512-5525.
Holschuh, T.V., Marcum, W.R., Morrell, S., Chichester, D.L. “Quantifying Kinetics Parameters using Cherenkov Light for Nonproliferation”, Institute of Nuclear Materials Management Annual Meeting, Atlanta, Georgia, United States, pp. 1-10. July 12-16, 2015.
Marcum, W.R., Weiss, A., Jones, W.F., Woolstenhulme, N., Phillips, A.M., Holdaway, K., Moussaoui, M., Harmon, P.L., Howard, T.K., Wiest, J., Campbell, J. “On the Characterization of a Drop-in Miniplate Experiment – Hydraulic Analysis”, 2015 American Nuclear Society Annual Meeting, San Antonio, Texas, United States, June 7-11, Vol. 112, pp. 907-910.
Jones, W.F., Marcum, W.R., Weiss, A., Howard, T.K., Woolstenhulme, N., Phillips, A.M., Wiest, J., “On the Characterization of a Drop-in Miniplate Experiment – Structural Response Analysis”, 2015 American Nuclear Society Annual Meeting, San Antonio, Texas, United States, June 7-11, Vol. 112, pp. 911-914.
Jackson, R.B., Woods, B.G., Marcum, W.R., “Boundary Layer Laminarization by Convex Curvature and Acceleration,” Nuclear Engineering and Design, Volume 278, pp. 693-700, October 2014.
Marcum, W.R., “Predicting Critical Flow Velocity Leading to Laminate Plate Collapse – Cylindrical Plates,” Nuclear Engineering and Design, Volume 278, pp. 50-63, October 2014.
Jensen, P., Marcum, W.R., “Predicting Critical Flow Velocity and Laminate Plate Collapse - Flat Plates,” Nuclear Engineering and Design, Volume 267, pp. 71-87, February 2014.
Holschuh, T.V., Marcum, W.R., Morrell, S. “Non-Proliferation Application of Off-the-shelf Detector(s) for Research Reactors”, Institute of Nuclear Materials Management Annual Meeting, Atlanta, Georgia, United States, pp. 1-10, July 20-24, 2014.
Holschuh, T.V., Howard, T.K., Marcum, W.R., “Deflection of a Heterogeneous Wide-Beam Under Uniform Pressure Load”, Advances in Thermal Hydraulics, 2014 American Nuclear Society Annual Conference, Reno, Nevada, United States, pp. 545-554, June 15-19, 2014.
Howard, T.K., Marcum, W.R., Jones, W.F., “Characterizing Virtual Mass Effects of a Submersed Body Using Pseudo-Fluid Elements”, Advances in Thermal Hydraulics, 2014 American Nuclear Society Annual Conference, Reno, Nevada, United States, June 15-19, pp. 593-605, 2014.
Zabriskie, A.X., Marcum, W.R., Wachs, D.M., “Initial Analysis of Transient Power Time Lag due to Heterogeneity within the TREAT Fuel Matrix”, Advances in Thermal Hydraulics, 2014 American Nuclear Society Annual Conference, Reno, Nevada, United States, June 15-19, pp. 583-592, 2014.
Marcum, W.R., Reese, S.R., Keller, S.T., Schickler, R.A., “Developing a Reactor Operator Training Course Series at Oregon State University”, 121st ASEE Annual Conference and Exposition, Indianapolis, Indiana, United States, June 15-18, pp. 1-10, 2014.
Harmon, P.L., Marcum, W.R., Liu, S., Moussaoui, M., Weiss, A., Jones, W.F., Woolstenhulme, N., “On the Natural Frequency of Fueled Experimental Plates in Air and Water – Experimental Study,” 2014 American Nuclear Society Winter Meeting, Vol. 111, pp. 1654-1655, 2014.
Britsch, K., Marcum, W.R., Howard, T.K., Harmon, P.L., “On the Natural Frequency of Fueled Experimental Plates in Air and Water – Numerical Study,” 2014 American Nuclear Society Winter Meeting, Vol. 111, pp. 1656-1657, 2014.
Howard, T.K., Marcum, W.R., Jones W.F., “A Novel Approach on Modeling Fluid Structure Interactions”, 2014 American Nuclear Society Winter Meeting, Vol. 111, pp. 1495-1498, 2014.
Tucker, J., Teeter, L., Teng, F., Marcum, W., Kruzic, J., Anderson, M., Hawk, J., Holcomb, G., Dogan, O., Jablonski, P., “Development of a Supercritical Carbon-Dioxide System for Materials Corrosion Testing,” 4th International Symposium Supercritical CO2 Power Cycles, Pittsburgh, Pennsylvania, United States, September 9-10, 2014.
Marcum, W.R., “Nuclear Power and its Position within the Future Energy Vertical,” International Journal of Advance Innovations, Thoughts & Ideas, Volume 2, Number 4, pp.1-2, October 2013.
Schickler, R., Marcum, W.R., Reese, S.R., “Comparison of HEU and LEU Neutron Spectra in Irradiation Facilities at the Oregon State TRIGA® Reactor,” Nuclear Engineering and Design, Volume 262, pp. 340-349, September 2013.
Hartman, M.R., Robinson, B., Keller, S.T., Stevens, J., Matos, J.E., Reese, S.R., Marcum, W.R., Palmer T.S., Woods, B.G., “Neutronic Analysis of the Oregon State TRIGA® Reactor,” Nuclear Science and Engineering, Volume 174, Number 2, pp. 135-149, June 2013.
Marcum, W.R., Weiss, A., Woods, B.G., “Hydro-Mechanical Testing of a Prototypic Fuel”, 15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Pisa, Italy, May 12-16, 2013.
Choi, J.H., Marcum, W.R., “Prediction of Hydro-Mechanical Behaviour in Reactor Core with a Plate-Type Fuel Assembly”, Fluid Structure Interaction 2013 – 7th Subrata Chakrabari International Conference on Fluid Structure Interaction, Gran Canaria, Spain, April 10-12, 2013
Howard, T.K., Marcum, W.R., “Characterization of the OSU HMFTF Piping System”, Trans. American Nuclear Society Winter Meeting, Vol. 109, pp. 1805-1807, 2013.
Goodrich S.S., Marcum, W.R., “Characterization of the Laser Imaging of Natural Circulation (LINC) Facility at Oregon State University”, Trans. American Nuclear Society Winter Meeting, Vol. 109, pp. 1793-1794, 2013.
Howard, T.K., Marcum, W.R., “Computational Fluid Dynamics Simulation of Vortex Shedding Between Inline Plates”, Trans. American Nuclear Society Annual Meeting, Vol. 108, pp. 998-1000, 2013.
Jensen, P., Marcum, W.R., “A Model to Predict Critical Flow Velocity for a Flat Laminate Plate”, Trans. American Nuclear Society Annual Meeting, Vol. 108, pp. 1035-1038, 2013.
Byfield, P., Marcum, W.R., “Steady State Thermal Hydraulic Analysis of a Molybdenum Production Element for Implementation in TRIGA® Reactors”, Trans. American Nuclear Society Annual Meeting, Vol. 108, pp. 967-969, 2013.
Jones, W.F., Snow, S.D., Howard, T., Marcum, W.R., “Simulation of Flow-Induced Vibration on a Multi-Plate Experiment in Water”, Trans. American Nuclear Society Annual Meeting, Vol. 108, pp. 1046-1049, 2013.
Marcum, W.R., Spinrad, B., Nuclear Reactors. In Encyclopedia Britannica. 2012.
Marcum, W.R., “Morphing from a Separate Effects to Multiphysics Characterization Environment,” Journal of Nuclear Energy Science & Power Generation Technology, Volume 1, Number 1, pp. 1-2, October 2012.
Marcum, W.R., Woods, B.G., “Predicting the Onset of Dynamic Instability of a Cylindrical Plate under Axial Flow Conditions,” Nuclear Engineering and Design, Volume 250, pp. 81-100, September 2012.
Marcum, W.R., Palmer, T.S., Woods, B.G., Keller, S.T., Reese, S.R., Hartman, M.R., “A Comparison of Pulsing Characteristics of the Oregon State University TRIGA® Reactor with FLIP and LEU Fuel,” Nuclear Science and Engineering, Volume 171, Number 2, pp. 150-164, June 2012.
Jackson, R.B., Woods, B.G., Marcum, W.R., “Boundary Layer Laminarization by Convex Curvature and Acceleration Effects”, Advances in Thermal Hydraulics, 2012 American Nuclear Society Winter Conference, San Diego, California, United States, pp. 246-255, November 11-15, 2012.
Holschuh, T., Weiss, A., Jensen, P., Marcum, W.R., “Proof-of-Concept: Method for Identifying Fuel Plate Plastic Deformation in Real Time”, Advances in Thermal Hydraulics, 2012 American Nuclear Society Winter Conference, San Diego, California, United States, pp. 232-241, November 11-15, 2012.
Jackson, R.B., Howard, T., Mullin, E., Marcum, W.R., “Preliminary Investigation on Vortical Structure Influence of Trailing Plate in Axial Flow”, Trans. American Nuclear Society Winter Meeting, Vol. 107, pp. 1333-1335, 2012.
Roth, G.D., Marcum, W.R., Woods, B.G., “CFD Study of the Generic Test Plate Assembly for use in the Hydro-Mechanical Fuel Test Facility”, Trans. American Nuclear Society Winter Meeting, Vol. 105, pp. 933-934, 2011.
Marcum, W.R., Phillips, A.M., Ambrosek, R.G., Spears, R.E., Wiest, J.D., “Method for Experimental Acquisition of Hydraulic Induced Plastic and Elastic Fuel Plate Deformation”, Trans. American Nuclear Society Winter Meeting, Vol. 105, pp. 968-969, 2011.
Marcum, W.R., Phillips, A.M., Wachs, D.M., “Shakedown Testing of the Hydro-Mechanical Fuel Test Facility,” 2011 Test, Research and Training Reactors, Idaho Falls, Idaho, United States, September 12-15, 2011.
Marcum, W.R., Woods, B.G., “Predicting the Onset of Dynamic Instability of a Cylindrical Plate under Axial Flow Conditions”, Trans. American Nuclear Society Annual Meeting, Vol. 104, pp. 1016-1017, 2011.
Marcum, W.R., Woods, B.G., Reese S.R., “Experimental and Theoretical Comparison of Fuel Temperature and Bulk Coolant Characteristics in the Oregon State TRIGA® Reactor during Steady State Operation,” Nuclear Engineering and Design, Volume 240, pp. 151-159, January 2010.
Marcum, W.R., Woods, B.G., Phillips, A.M., Ambrosek, R.G., Wiest, J.D., “The OSU Hydro-Mechanical Fuel Test Facility: Standard Fuel Element Testing” International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR 2010), Lisbon, Portugal, October 10-14, 2010.
Roth, G.D., Marcum, W.R., Woods, B.G., “The Deflection of Plate Type Fuel During Facility Ramp-up”, Trans. American Nuclear Society Winter Meeting, Vol. 103, pp. 1026-1027, 2010.
Marcum, W.R., Woods, B.G., “Flow Assessment of the Hydro-Mechanical Fuel Test Facility at Oregon State University,” Trans. American Nuclear Society Winter Meeting, Vol. 103, pp. 1013-1014, 2010.
Marcum, W.R., Woods, B.G., Hartman, M.R., Reese, S.R., Palmer, T.S., Keller, S.T., “Steady-State Thermal-Hydraulic Analysis of the Oregon State University TRIGA Reactor Using RELAP5-3D,” Nuclear Science and Engineering, Volume 162, Number 3, pp. 261-274, July 2009.
Keller, S.T., Marcum, W.R., Woods, B.G., Reese, S.R., Palmer, T.S., Hartman, M.R., Matos, J.E., Stevens, J., Dunn, F.E., Feldman E.E., “Oregon State TRIGA® Reactor Conversion Analysis Highlights,” International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR 2009), Beijing, China, November 1-5, 2009.
Marcum, W.R., Arnold, A.C., Woods, B.G., Wachs, D.M., “Implementation of RELAP5-3D System Model to Supplement the Design of the Hydro-Mechanical Fuel Test Facility,” International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR 2009), Beijing, China, November 1-5, 2009.
Marcum, W.R., Woods, B.G., “Numerical Flow Sensitivity Study of Instrumentation in the Hydro-Mechanical Fuel Test Facility Test Section using FLUENT®,” Trans. American Nuclear Society Winter Meeting, Vol. 101, pp. 942-943, 2009.
Marcum, W.R., Woods, B.G., Jackson, R.B., “Numerical Flow Benchmark Model of Advanced Test Reactor Fuel Element Using FLUENT®,” Trans. American Nuclear Society Annual Meeting, Vol. 100, pp. 683-684, 2009.
Marcum, W.R., Woods, B.G., Wachs, D.M., “High Performance Research Reactor Fuel Development Hydraulic Test Loop,” International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR 2008), Washington D.C., United States, October 5-9, 2008.
Marcum, W.R., Woods, B.G., Hartman, M.R., “Thermal Hydraulic Analysis for the Oregon State TRIGA Reactor Using RELAP5-3D,” International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR 2007), Prague, Czech Republic, September 23-27, 2007.
Marcum, W.R., Woods, B.G., “Thermal Hydraulic Analysis of Oregon State University TRIGA® Reactor using RELAP5-3D,” Trans. American Nuclear Society Winter Meeting, Vol. 97, pp. 791-792, 2007.
Marcum, W.R., Woods, B.G., “Thermal Hydraulic Analysis of Oregon State University TRIGA® Reactor using RELAP5-3D,” 2007 Test, Research and Training Reactors, Lincoln City, Oregon, United States, September 17-20, 2007.