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N.E. Todreas

Observed names: N E Todreas, N Todreas, N. E. TODREAS, N. E. Todreas, N. Todreas, N. Todreas (mit, N.E.Todreas, N.E.Todreas Netodreas, Neil E Todreas, Neil E. Todreas, Neil Todreas, Professor Neil Todreas, TODREAS N., TODREAS N. E., Todreas, N., Todreas, N. E., Todreas, N.E., Todreas, Neil, Todreas, Neil E, Todreas, Neil E., Todreas, Neil E. author.
Observed institutions: Northwestern University, Southwest Research Institute, National Institute of Standards and Technology, United States Department of Commerce, Pacific Northwest National Laboratory, Brookhaven National Laboratory, National Technical Information Service, Laboratoire des Écoulements Géophysiques et Industriels, Électricité de France (France), United States Atomic Energy Commission, Electrical Research and Development Association, Massachusetts Institute of Technology, Catholic University of America, Politecnico di Milano
OpenAlex ID: A5111458776
Hydrodynamic models and correlations for bare and wire-wrapped hexagonal rod bundles — Bundle friction factors, subchannel friction factors and mixing parameters
1986 · Shih-Kuei Cheng, Neil E. Todreas · Nuclear Engineering and Design · 427
The design and safety features of the IRIS reactor
2004 · Mario D. Carelli, L.E. Conway, et al. · Nuclear Engineering and Design · 304
An experimental investigation of a passive cooling unit for nuclear plant containment
2000 · H. Liu, N.E. Todreas, et al. · Nuclear Engineering and Design · 167
The Offshore Floating Nuclear Plant Concept
2016 · J. Buongiorno, J. Jurewicz, et al. · Nuclear Technology · 139
Nuclear Systems Volume I: Thermal Hydraulic Fundamentals
2020 · Neil E. Todreas, Mujid S. Kazimi · CRC Press eBooks · 124
The upgraded Cheng and Todreas correlation for pressure drop in hexagonal wire-wrapped rod bundles
2018 · S.K. Chen, Y.M. Chen, et al. · Nuclear Engineering and Design · 122
A Supercritical CO2 Gas Turbine Power Cycle for Next-Generation Nuclear Reactors
2002 · Vaclav Dostal, Michael J. Driscoll, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 115
Evaluation of existing correlations for the prediction of pressure drop in wire-wrapped hexagonal array pin bundles
2013 · S.K. Chen, N.E. Todreas, et al. · Nuclear Engineering and Design · 94
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Thermal Analysis of Pressurized Water Reactors
1980 · Neil E. Todreas · International Journal of Multiphase Flow · 88
SUPERENERGY-2: a multiassembly, steady-state computer code for LMFBR core thermal-hydraulic analysis
1980 · K.L. Basehore, N.E. Todreas · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 79
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Experimental and Analytical Study of Axial Turbulent Flows in an Interior Subchannel of a Bare Rod Bundle
1976 · P. Carajilescov, N. E. Todreas · ASME Journal of Heat and Mass Transfer · 77
Distributed resistance modeling of wire-wrapped rod bundles
1987 · Hisashi Ninokata, Apostolos Efthimiadis, et al. · Nuclear Engineering and Design · 74
Nuclear Systems Volume I
2011 · Neil E. Todreas, Mujid Kazimi · CRC Press eBooks · 69
Safety Analysis of a 300-MW(electric) Offshore Floating Nuclear Power Plant in Marine Environment
2018 · Yaoli Zhang, Jacopo Buongiorno, et al. · Nuclear Technology · 58
Nuclear systems 1
1990 · N.E. Todreas, M.J. Kazami · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 55
Experimental evaluation of pressure drop in round tubes provided with physically separated, multiple, short-length twisted tapes
2011 · P. Ferroni, R.E. Block, et al. · Experimental Thermal and Fluid Science · 51
A porous body model for predicting temperature distribution in wire-wrapped fuel rod assemblies
1975 · E.U. Khan, W.M. Rohsenow, et al. · Nuclear Engineering and Design · 50
An assessment of two-phase pressure drop correlations for steam-water systems
1977 · W. Idsinga, N. Todreas, et al. · International Journal of Multiphase Flow · 47
Effective Thermal Conductivity and Edge Conductance Model for a Spent-Fuel Assembly
1994 · Randall D. Manteufel, Neil E. Todreas · Nuclear Technology · 45
Thermal Contact Conductance in Reactor Fuel Elements
1973 · Gary Jacobs, Neil Todreas · Nuclear Science and Engineering · 44
Conceptual design and analysis of a semi-passive containment cooling system for a large concrete containment
2000 · C.S. Byun, D.W. Jerng, et al. · Nuclear Engineering and Design · 43
Cross-comparison of fast reactor concepts with various coolants
2009 · Pavel Hejzlar, Neil E. Todreas, et al. · Nuclear Engineering and Design · 41
Buoyancy and Property Variation Effects in Turbulent Mixed Convection of Water in Vertical Tubes
1996 · Y. Parlatan, N. E. Todreas, et al. · ASME Journal of Heat and Mass Transfer · 38
Consideration of critical heat flux margin prediction by subcooled or low quality critical heat flux correlations
1996 · Pavel Hejzlar, Neil E. Todreas · Nuclear Engineering and Design · 37
Advanced Light-Water Reactors
1990 · Michael W. Golay, Neil E. Todreas · Scientific American · 37
Works count: 432
Citation count: 4,219
H-index: 32
I10-index: 89
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