关注
Wade Marcum
Wade Marcum
在 oregonstate.edu 的电子邮件经过验证
标题
引用次数
引用次数
年份
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
352019
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
232010
Thermal hydraulic analysis of the Oregon State TRIGA Reactor using RELAP5-3D
WR Marcum
232008
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
212013
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
212009
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
182015
Predicting critical flow velocity leading to laminate plate collapse—flat plates
P Jensen, WR Marcum
Nuclear Engineering and Design 267, 71-87, 2014
172014
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
152015
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
142016
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
142012
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
102019
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
102015
High performance research reactor fuel development hydraulic test loop
WR Marcum, BG Woods, DM Wachs
RERTR 2008, 2008
92008
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
92001
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
82020
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
82020
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
82013
Quantifying oxide layer growth at low pressures and temperatures for aluminum alloy 6061
JD Tucker, Y Wei, WR Marcum, PV Murkute, BJ Gibbons, OB Isgor
Metallurgical and Materials Transactions A 50, 3388-3398, 2019
72019
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
72018
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
72012
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