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Neil E. Todreas

Neil E. Todreas

KEPCO Professor of Nuclear Science and Engineering, and Professor of Mechanical Engineering
(Emeritus)

todreas@mit.edu
617-253-5296
617-258-8863 (fax)
24-216A

Education

B.S., Mechanical Engineering, Cornell University, 1957
M.S., Mechanical Engineering,Cornell University, 1958
Sc.D., Nuclear Engineering, Massachusetts Institute of Technology, 1966

Research Interests

Thermal hydraulic aspects of nuclear systems performance under steady-state and accident conditions, advanced light water reactor (LWR) and fast reactor concepts, and safety features of operating LWRs of western design.

Current Research Interests

Student participation in all projects requires nuclear engineering course preparation.

Innovative Water Reactor Concepts

The goal of the efforts is to achieve long life core with a high degree of passive safety and greatly reduced capital cost and to explore the use of solid hydride fuel in PWR and BWRs. Means to achieve physical protection of these reactors is also of interest.

Sodium and Gas Cooled Fast Reactor Design

This work investigates design options for these fast reactors to improve their economic competitiveness while retaining safety features sufficient to meet safe performance needs. The safety structure being applied is the new US regulatory technology neutral framework which presents new criteria for evaluating innovative design features.

Ice Condenser Containment

The ice loading in these containments has led to a series of costly maintenance and design basis issues because of its sublimation and blockage of flow paths. The concept of replacing this ice with thin solid structure to absorb energy appears promising and merits further exploration.

Thermal Analysis of Waste Fuel in Storage and Transportation

Horizontal rod bundles in storage and transportation must be kept under certain maximum temperatures. Prediction methods and experimental data for such arrays exist. New input for the benchmark industry code used for these analyses have developed but need to be adjusted and validated based on comparison with existing experimental data.

Honors and Awards

  • Outstanding Professor Award, Nuclear Science and Engineering Department: 1975, 1976, 1980, 1996, 2011
  • American Nuclear Society Best Paper Award, Thermal-Hydraulic Division, 1987
  • National Heat Transfer Conference Best Paper Award, 1987
  • American Nuclear Society Technical Achievement Award, Thermal-Hydraulic Division, 1994
  • MIT School of Engineering Ruth & Joel Spira Award for Distinguished Teaching, 1995
  • American Nuclear Society Arthur Holly Compton Award, 1995
  • ICONE 8 Conference, A Thermal Hydraulic Track Best Paper Award, 1999
  • Inaugural Lecture, Distinguished Lecture Series of the Department of Mechanical & Nuclear Engineering, Pennsylvania State University, 2001
  • Inaugural Lecture, O'Hanian Engineering Lecture Series, University of Florida, 2002
  • Henry DeWolf Smyth Nuclear Statesman Award, 2005

Other Professional Activities

  • Fellow, American Nuclear Society, 1981
  • Fellow, American Society of Mechanical Engineers, 1983
  • Member, National Academy of Engineering, 1988
  • Chair, Korea Electric Power Corp. Professor of Nuclear Engineering, 1992-2006

Selected Recent Publications

Books

  1. M. Gavrilas, P. Hejzlar, Y. Shatilla, and N. E. Todreas, "Safety Features of Operating Light Water Reactors of Western Design," CRC Press, 1995.
  2. N. E. Todreas and M. S. Kazimi, "Nuclear Systems: Vol. I, Thermal Hydraulic Fundamentals," Hemisphere, NY 1990, 3rd printing, Taylor & Francis, 2001; and Nuclear Systems: Vol. II, Elements of Thermal Hydraulic Design, Hemisphere, NY, 1990.

Papers/Presentations

  1. N. E. Todreas, P. Hejzlar, A. Nikiforova, R. Petroski, E. Shwageraus, C. J. Fong, M. J. Driscoll, M. A. Elliott, G. Apostolakis, “Flexible Conversion Ratio Fast Reactors: Overview,” Nuclear Engineering and Design, Special Issue on Flexible Conversion Fast Reactors, Vol. 239, No. 12, pp.2582-2596, Dec. 2009.
  2. A. Nikiforova, P. Hejzlar, N. E. Todreas, “Lead-Cooled Flexible Conversion Ratio Fast Reactor,” Nuclear Engineering and Design, Special Issue on Flexible Conversion Fast Reactors, Vol. 239, No. 12, pp.2596-2611, Dec. 2009.
  3. R. Petroski, P. Hejzlar, N. E. Todreas, “Thermal Hydraulic Design of a Liquid Salt-Cooled Flexible Conversion Ratio Fast Reactor,” Nuclear Engineering and Design, Special Issue on Flexible Conversion Fast Reactors, Vol. 239, No. 12, pp.2612-2625, Dec. 2009.
  4. C. J. Fong, G. E. Apostolakis, D. R. Langewisch, P. Hejzlar, N. E. Todreas, M. J. Driscoll, “Reliability Analysis of a Passive Cooling System Using a Response Surface with an Application to the Flexible Conversion Ratio Reactor,” Nuclear Engineering and Design, Special Issue on Flexible Conversion Fast Reactors, Vol. 239, No. 12, pp.2660-2671, Dec. 2009.
  5. P. Hejzlar, N. E. Todreas, E. Shwageraus, A. Nikiforova, R. Petroski, M. J. Driscoll, “Cross-Comparison of Fast Reactor Concepts with Various Coolants,” Nuclear Engineering and Design, Special Issue on Flexible Conversion Fast Reactors, Vol. 239, No. 12, pp.2672-1691, Dec. 2009.
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  7. Denman, M., N. Todreas, M. Driscoll, “Risk Informed Design Choices Using the Technology Neutral Framework,” Transactions of the American Nuclear Society, Vol. 101, pp.503-504, 2009.
  8. E. Greenspan, M. Fratoni, F. Ganda, F. Ginex, D. Olander, N. Todreas, P. Diller, P. Ferroni, J. Malen, A. Romano, C. Shuffler, J. Trant, B. Petrovic, H. Garkisch, “Hydride Fuel for LWRs – Project Overview,” Nuclear Engineering and Design, Special Issue on Hydride Fueled LWRs, Vol. 239, No. 8, pp.1374-1405, August 2009.
  9. C. Shuffler, J. Trant, J. Malen, N. Todreas, “Thermal Hydraulic Analysis for Grid Supported Pressurized Water Reactor Cores,” Nuclear Engineering and Design, Special Issue on Hydride Fueled LWRs, Vol. 239, No. 8, pp.1442-1460, August 2009.
  10. P. Diller, N. Todreas, P. Hejzlar, “Thermal-Hydraulic Analysis for Wire-Wrapped PWR Cores,” Nuclear Engineering and Design, Special Issue on Hydride Fueled LWRs, Vol. 239, No. 8, pp.1461-1470, August 2009.
  11. J. A. Malen, N. E. Todreas, P. Hejzlar, P. Ferroni, A. Bergles, “Thermal Hydraulic Design of a Hydride-Fueled Inverted PWR Core,” Nuclear Engineering and Design, Special Issue on Hydride Fueled LWRs, Vol. 239, No. 8, pp.1471-1480, August 2009.
  12. A. Romano, C. A. Shuffler, H. D. Garkisch, D. R. Olander, N. E. Todreas, “Fuel Performance Analysis for PWR Cores,” Nuclear Engineering and Design, Special Issue on Hydride Fueled LWRs, Vol. 239, No. 8, pp.1481-1488, August 2009.
  13. C. Shuffler, P. Diller, J. Malen, N. Todreas, E. Greenspan, B. Petrovic, “Economic Analysis of Grid and Wire Wrap Supported Hydride and Oxide Fueled Pressurized Water Reactors,” Nuclear Engineering and Design, Special Issue on Hydride Fueled LWRs, Vol. 239, No. 8, pp.1505-1530, August 2009.
  14. P. Ferroni, C. S. Handwerk, N. E. Todreas, “Steady State Thermal-Hydraulic Analysis of Hydride-Fueled Grid-Supported BWRs,” Nuclear Engineering and Design, Special Issue on Hydride Fueled LWRs, Vol. 239, No. 8, pp.1544-1559, August 2009.

Teaching

22.39 Integration of Reactor Design, Operations, and Safety
22.313J Thermal Hydraulics in Power Technology

Recent News


NEW: Second Edition


book cover
Nuclear Systems Volume I: Thermal Hydraulic Fundamentals, 2nd ed.
Updated with new information about advanced nuclear fuel designs, two-phase flow and heat transfer, and pre- and post- accident energy sources in nuclear plants.

Massachusetts Institute of Technology

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