| Natural convection heat transfer and boundary layer transition for vertical heated cylinders SS Goodrich, WR Marcum Experimental Thermal and Fluid Science 105, 367-380, 2019 | 33 | 2019 |
| Experimental and theoretical comparison of fuel temperature and bulk coolant characteristics in the Oregon State TRIGA® reactor during steady state operation WR Marcum, BG Woods, SR Reese Nuclear Engineering and Design 240 (1), 151-159, 2010 | 24 | 2010 |
| Thermal hydraulic analysis of the Oregon State TRIGA Reactor using RELAP5-3D WR Marcum | 23 | 2008 |
| Steady-state thermal-hydraulic analysis of the Oregon State University TRIGA reactor using RELAP5-3D WR Marcum, BG Woods, MR Hartman, SR Reese, TS Palmer, ST Keller Nuclear science and engineering 162 (3), 261-274, 2009 | 21 | 2009 |
| Comparison of HEU and LEU neutron spectra in irradiation facilities at the Oregon State TRIGA® Reactor RA Schickler, WR Marcum, SR Reese Nuclear Engineering and Design 262, 340-349, 2013 | 20 | 2013 |
| Applying uncertainty and sensitivity on thermal hydraulic subchannel analysis for the multi-application small light water reactor WR Marcum, AJ Brigantic Nuclear Engineering and Design 293, 272-291, 2015 | 18 | 2015 |
| Predicting critical flow velocity leading to laminate plate collapse—flat plates P Jensen, WR Marcum Nuclear Engineering and Design 267, 71-87, 2014 | 16 | 2014 |
| The effect of jet location and duty cycle on the fluid mechanics of an unconfined free jet and its heat transfer on an impinging plate WR Marcum, SR Cadell, C Ward International Journal of Heat and Mass Transfer 88, 470-480, 2015 | 15 | 2015 |
| A comparison of pulsing characteristics of the Oregon State University TRIGA reactor with FLIP and LEU fuel WR Marcum, TS Palmer, BG Woods, ST Keller, SR Reese, MR Hartman Nuclear science and engineering 171 (2), 150-164, 2012 | 14 | 2012 |
| Aluminum cladding oxidation of prefilmed in-pile fueled experiments WR Marcum, DM Wachs, AB Robinson, MA Lillo Journal of Nuclear Materials 471, 136-148, 2016 | 13 | 2016 |
| A coupled multiscale approach to TREAT LEU feedback modeling using a binary-collision Monte-Carlo–informed heat source A Zabriskie, S Schunert, D Schwen, J Ortensi, B Baker, Y Wang, ... Nuclear Science and Engineering 193 (4), 368-387, 2019 | 10 | 2019 |
| A novel approach to modeling plate deformations in fluid–structure interactions TK Howard, WR Marcum, WF Jones Nuclear Engineering and Design 293, 1-15, 2015 | 10 | 2015 |
| High performance research reactor fuel development hydraulic test loop WR Marcum, BG Woods, DM Wachs RERTR 2008, 2008 | 9 | 2008 |
| The OSU Hydro-Mechanical Fuel Test Facility: Standard Fuel Element Testing WR Marcum, BG Woods, AM Phillips, RG Ambrosek, JD Wiest, DM Wachs Idaho National Lab.(INL), Idaho Falls, ID (United States), 2001 | 9 | 2001 |
| A novel method for predicting power transient CHF via the heterogeneous spontaneous nucleation trigger mechanism E Brown, Y Yan, WR Marcum Nuclear Technology 206 (9), 1296-1307, 2020 | 8 | 2020 |
| Developing Separate Effects Transient Test Experiments Using an Out-of-Pile Flowing Water Loop W Marcum, D LaBrier, E Brown, Y Yan, N Woolstenhulme Nuclear Technology 206 (6), 895-910, 2020 | 8 | 2020 |
| Neutronic Analysis of the Oregon State TRIGA Reactor in Support of Conversion from HEU Fuel to LEU Fuel MR Hartman, ST Keller, SR Reese, B Robinson, J Stevens, JE Matos, ... Nuclear Science and Engineering 174 (2), 135-149, 2013 | 8 | 2013 |
| Reducing uncertainty in hydrodynamic modeling of ATR experiments via flow testing, validation, and optimization WF Jones, WR Marcum, AW Weiss, CB Jensen, GL Hawkes, PE Murray, ... Nuclear Technology 201 (3), 286-303, 2018 | 7 | 2018 |
| OSU HMFTF Facility Description Report WR Marcum Technical report. OSU-HMFTF-000000-TECH-003, 2011 | 7 | 2011 |
| On the fluid structure interactions of a wire-wrapped pin bundle CA Nixon, WR Marcum, KM Steer, RB Jackson, MG Martin, AW Weiss Nuclear Technology 206 (2), 218-230, 2020 | 6 | 2020 |
