Wade Marcum
Wade Marcum
Verified email at oregonstate.edu
Cited by
Cited by
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
Thermal hydraulic analysis of the Oregon State TRIGA Reactor using RELAP5-3D
WR Marcum
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
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
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
Predicting critical flow velocity leading to laminate plate collapse—flat plates
P Jensen, WR Marcum
Nuclear Engineering and Design 267, 71-87, 2014
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
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
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
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
High performance research reactor fuel development hydraulic test loop
WR Marcum, BG Woods, DM Wachs
RERTR 2008, 2008
OSU HMFTF Facility Description Report
WR Marcum
Technical report. OSU-HMFTF-000000-TECH-003, 2011
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
Predicting the onset of dynamic instability of a cylindrical plate under axial flow conditions
WR Marcum, BG Woods
Nuclear engineering and design 250, 81-100, 2012
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
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
Modified Fuchs-Nordheim model for use in reactor pulse measurements
TV Holschuh, WR Marcum
Annals of Nuclear Energy 116, 314-318, 2018
Reactor physics scoping and characterization study on implementation of TRIGA fuel in the Advanced Test Reactor
JA Lyons, WR Marcum, S Morrell, M DeHart
Nuclear Technology 189 (2), 202-217, 2015
Predicting critical flow velocity leading to laminate plate collapse–Cylindrical plates
WR Marcum
Nuclear Engineering and Design 278, 50-63, 2014
Predicting Mechanical Instability of a Cylindrical Plate under Axial Flow Conditions
WR Marcum
Oregon State University, 2010
The system can't perform the operation now. Try again later.
Articles 1–20