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Neil Emmanuel Todreas

Affiliations: 
Nuclear engineering Massachusetts Institute of Technology, Cambridge, MA, United States 
Area:
Nuclear engineering
Website:
http://meche.mit.edu/people/faculty/todreas@mit.edu
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"Neil Emmanuel Todreas"
Bio:

Todreas, Neil Emmanuel, The effect of nonuniform axial heat flux distribution on the critical heat flux. Massachusetts Institute of Technology. Dept. of Nuclear Engineering. Thesis. 1966. Sc.D.

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Parents

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Warren Max Rohsenow grad student 1966 MIT
 (The effect of nonuniform axial heat flux distribution on the critical heat flux.)

Children

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Mujid S. Kazimi grad student 1973 MIT
Michael L. Corradini grad student 1979 MIT

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Publications

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Aksan N, Andreani M, Bechta S, et al. (2019) The life and the contribution of B. R. Sehgal, G. Yadigaroglu and G. Hewitt: Remembrance statements Nuclear Engineering and Design. 354: 110252
Otgonbaatar U, Baglietto E, Todreas N. (2016) Methodology for Characterizing Representativeness Uncertainty in Orifice Plate Mass Flow Rate Measurements Using CFD Simulations Nuclear Science and Engineering. 184: 430-440
Shirvan K, Ballinger R, Buongiorno J, et al. (2015) Technology Selection for Offshore Underwater Small Modular Reactors Nuclear Engineering and Technology
Arment TW, Todreas NE, Bergles AE. (2013) Critical heat flux and pressure drop for tubes containing multiple short-length twisted-tape swirl promoters Nuclear Engineering and Design. 257: 1-11
Ferroni P, Block RE, Todreas NE, et al. (2011) Experimental evaluation of pressure drop in round tubes provided with physically separated, multiple, short-length twisted tapes Experimental Thermal and Fluid Science. 35: 1357-1369
Todreas NE. (2009) Thermal-Hydraulic Challenges in Fast Reactor Design Nuclear Technology. 167: 127-144
Todreas NE, Hejzlar P, Nikiforova A, et al. (2009) Flexible conversion ratio fast reactors: Overview Nuclear Engineering and Design. 239: 2582-2595
Nikiforova A, Hejzlar P, Todreas NE. (2009) Lead-cooled flexible conversion ratio fast reactor Nuclear Engineering and Design. 239: 2596-2611
Petroski R, Hejzlar P, Todreas NE. (2009) Thermal hydraulic design of a liquid salt-cooled flexible conversion ratio fast reactor Nuclear Engineering and Design. 239: 2612-2625
Fong CJ, Apostolakis GE, Langewisch DR, et al. (2009) Reliability analysis of a passive cooling system using a response surface with an application to the flexible conversion ratio reactor Nuclear Engineering and Design. 239: 2660-2671
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