Showing 1 - 20 results of 40 for search 'Todreas, Neil E', query time: 0.04s Refine Results
  1. 1
    22.312 Engineering of Nuclear Reactors, Fall 2002

    22.312 Engineering of Nuclear Reactors, Fall 2002 by Todreas, Neil E.

    Published 2002
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    Learning Object
  2. 2
    22.313 Thermal Hydraulics in Nuclear Power Technology, Spring 2003

    22.313 Thermal Hydraulics in Nuclear Power Technology, Spring 2003 by Todreas, Neil E.

    Published 2003
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    Learning Object
  3. 3
    Nuclear systems /

    Nuclear systems / by Todreas, Neil E., Kazimi, Mujid S.

    Published 2012
  4. 4
    Nuclear systems [electronic resource] /

    Nuclear systems [electronic resource] / by Todreas, Neil E., Kazimi, Mujid S.

    Published 2012
  5. 5
    The comparison of available data on PWR assembly thermal behavior with analytical predictions

    The comparison of available data on PWR assembly thermal behavior with analytical predictions by Liu, J., Todreas, Neil E.

    Published 2006
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    Technical Report
  6. 6
    Wire Wrapped Hexagonal Pin Arrays for Hydride Fueled PWRs

    Wire Wrapped Hexagonal Pin Arrays for Hydride Fueled PWRs by Diller, Peter, Todreas, Neil E.

    Published 2012
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    Technical Report
  7. 7
    Selection of Correlations and Look-Up Tables for Critical Heat Flux Prediction in the Generation IV "IRIS" Reactor

    Selection of Correlations and Look-Up Tables for Critical Heat Flux Prediction in the Generation IV "IRIS" Reactor by Romano, A., Todreas, Neil E.

    Published 2012
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    Technical Report
  8. 8
    Transient thermal analysis of PWR’s by a single-pass procedure using a simplified nodal layout

    Transient thermal analysis of PWR’s by a single-pass procedure using a simplified nodal layout by Liu, Jack S. H., Todreas, Neil E.

    Published 2006
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    Technical Report
  9. 9
    The comparison of available data on PWR assembly thermal behavior with analytical predictions

    The comparison of available data on PWR assembly thermal behavior with analytical predictions by Liu, Jack S. H., Todreas, Neil E.

    Published 2006
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    Technical Report
  10. 10
    A four-equation two-phase flow model for sodium boiling simulation of LMFBR fuel assemblies

    A four-equation two-phase flow model for sodium boiling simulation of LMFBR fuel assemblies by Schor, Andrei L., Todreas, Neil E.

    Published 2011
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  11. 11
    COBRA IIIcMIT-2 : a digital computer program for steady state and transient thermal-hydraulic analysis of rod bundle nuclear fuel elements

    COBRA IIIcMIT-2 : a digital computer program for steady state and transient thermal-hydraulic analysis of rod bundle nuclear fuel elements by Jackson, J. W., Todreas, Neil E.

    Published 2011
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  12. 12
    A four-equation two-phase flow model for sodium boiling simulation of LMFBR fuel assemblies

    A four-equation two-phase flow model for sodium boiling simulation of LMFBR fuel assemblies by Schor, Andrei L., Todreas, Neil E.

    Published 2011
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  13. 13
    The effect of nonuniform axial heat flux distribution on the critical heat flux

    The effect of nonuniform axial heat flux distribution on the critical heat flux by Todreas, Neil E., Rohsenow, Warren M.

    Published 2011
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    Technical Report
  14. 14
    A review of recent analytical and experimental studies applicable to LMFBR fuel and blanket assembly design / by E. Khan and N. Todreas

    A review of recent analytical and experimental studies applicable to LMFBR fuel and blanket assembly design / by E. Khan and N. Todreas by Khan, Eshan Ullah, Todreas, Neil E.

    Published 2014
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    Technical Report
  15. 15
    An experiment to simulate the heat transfer properties of a dry, horizontal spent nuclear fuel assembly

    An experiment to simulate the heat transfer properties of a dry, horizontal spent nuclear fuel assembly by Lovett, Phyllis Maria, Todreas, Neil E.

    Published 2014
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    Technical Report
  16. 16
    FUEL PERFORMANCE ANALYSIS OF EXTENDED OPERATING CYCLES IN EXISTING LWRs

    FUEL PERFORMANCE ANALYSIS OF EXTENDED OPERATING CYCLES IN EXISTING LWRs by Handwerk, C. S., Meyer, J. E., Todreas, Neil E.

    Published 2012
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    Technical Report
  17. 17
    Vented Inverted Fuel Assembly Design for an SFR

    Vented Inverted Fuel Assembly Design for an SFR by Vitillo, Francesco, Todreas, Neil E., Driscoll, Michael J.

    Published 2012
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    Technical Report
  18. 18
    Development of a method for BWR subchannel analysis

    Development of a method for BWR subchannel analysis by Faya, Artur José Goncalves, Wolf, Lothar, Todreas, Neil E.

    Published 2006
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    Technical Report
  19. 19
    CANAL user's manual

    CANAL user's manual by Faya, Artur José Goncalves, Wolf, Lothar, Todreas, Neil E.

    Published 2006
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    Technical Report
  20. 20
    Plant Design and Cost Assessment of Forced Circulation Lead-Bismuth Cooled Reactor with Conventional Power Conversion Cycles

    Plant Design and Cost Assessment of Forced Circulation Lead-Bismuth Cooled Reactor with Conventional Power Conversion Cycles by Dostal, Vaclav, Hejzlar, Pavel, Todreas, Neil E., Kazimi, Mujid S.

    Published 2011
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    Technical Report

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