Neil E. Todreas : rechercher sur Z-Library

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1

Hydrodynamic models and correlations for bare and wire-wrapped hexagonal rod bundles — Bundle friction factors, subchannel friction factors and mixing parameters

Shih-Kuei Cheng, Neil E. Todreas

Journal:

Nuclear Engineering and Design

Année:

1986

Langue:

english

Fichier:

PDF, 1.45 MB

english, 1986

2

Advanced Light-Water Reactors

Golay, Michael W., Todreas, Neil E.

Journal:

Scientific American

Année:

1990

Langue:

english

Fichier:

PDF, 879 KB

english, 1990

3

Thermal-Hydraulic Challenges in Fast Reactor Design

Todreas, Neil E.

Journal:

Nuclear Technology

Année:

2009

Langue:

english

Fichier:

PDF, 795 KB

english, 2009

4

Safety Analysis of a 300-MW(electric) Offshore Floating Nuclear Power Plant in Marine Environment

Zhang, Yaoli, Buongiorno, Jacopo, Golay, Michael, Todreas, Neil

Journal:

Nuclear Technology

Année:

2018

Langue:

english

Fichier:

PDF, 2.65 MB

english, 2018

5

Distributed resistance modeling of wire-wrapped rod bundles

Hisashi Ninokata, Apostolos Efthimiadis, Neil E. Todreas

Journal:

Nuclear Engineering and Design

Année:

1987

Langue:

english

Fichier:

PDF, 657 KB

english, 1987

6

Passive decay heat removal in advanced LWR concepts

Pavel Hejzlar, Neil E. Todreas, Michael J. Driscoll

Journal:

Nuclear Engineering and Design

Année:

1993

Langue:

english

Fichier:

PDF, 1.64 MB

english, 1993

7

Consideration of critical heat flux margin prediction by subcooled or low quality critical heat flux correlations

Pavel Hejzlar, Neil E. Todreas

Journal:

Nuclear Engineering and Design

Année:

1996

Langue:

english

Fichier:

PDF, 559 KB

english, 1996

8

An economically optimum PWR reload core for a 36-month cycle

Luis Garcia-Delgado, Michael J Driscoll, John E Meyer, Neil E Todreas

Journal:

Annals of Nuclear Energy

Année:

1999

Langue:

english

Fichier:

PDF, 307 KB

english, 1999

9

Mixed convection friction factors and nusselt numbers in vertical annular and subchannel geometries

Victor Iannello, Kune Y. Suh, Neil E. Todreas

Journal:

International Journal of Heat and Mass Transfer

Année:

1988

Langue:

english

Fichier:

PDF, 1.48 MB

english, 1988

10

Response to Letter to the Editor on the round table discussion on reactor power margins published in Nuclear Engineering and Design 163 (1–2) 1996

Pavel Hejzlar, Neil E Todreas

Journal:

Nuclear Engineering and Design

Année:

2000

Langue:

english

Fichier:

PDF, 73 KB

english, 2000

11

Technology Selection for Offshore Underwater Small Modular Reactors

Shirvan, Koroush, Ballinger, Ronald, Buongiorno, Jacopo, Forsberg, Charles, Kazimi, Mujid, Todreas, Neil

Journal:

Nuclear Engineering and Technology

Année:

2016

Langue:

english

Fichier:

PDF, 1.94 MB

english, 2016

12

Thermal Contact Conductance in Reactor Fuel Elements

Jacobs, Gary, Todreas, Neil

Journal:

Nuclear Science and Engineering

Année:

1973

Langue:

english

Fichier:

PDF, 1.03 MB

english, 1973

13

Turbulent Flow Split Model and Supporting Experiments for Wire-Wrapped Core Assemblies

Chiu, Chong, Todreas, Neil E., Rohsenow, Warren M.

Journal:

Nuclear Technology

Année:

1980

Langue:

english

Fichier:

PDF, 1.01 MB

english, 1980

14

Single phase transport within bare rod arrays at laminar, transition and turbulent flow conditions

Hartmut Ramm, Klaus Johannsen, Neil E Todreas

Journal:

Nuclear Engineering and Design

Année:

1974

Langue:

english

Fichier:

PDF, 1.29 MB

english, 1974

15

Prediction of the coolant temperature field in a breeder reactor including interassembly heat transfer

Brian Cheng-jean Chen, Neil E. Todreas

Journal:

Nuclear Engineering and Design

Année:

1975

Langue:

english

Fichier:

PDF, 1002 KB

english, 1975

16

Models for the fluid-solid interaction force for multidimensional single phase flow within tube bundles

Derek B. Ebeling-Koning, James T. Robinson, Neil E. Todreas

Journal:

Nuclear Engineering and Design

Année:

1986

Langue:

english

Fichier:

PDF, 719 KB

english, 1986

17

Foreword

Neil E. Todreas, Chong Chiu

Journal:

Nuclear Engineering and Design

Année:

1987

Langue:

english

Fichier:

PDF, 50 KB

english, 1987

18

Energy transfer mechanisms in LMR rod bundles under mixed convection conditions

Tae Sun Ro, Neil E. Todreas

Journal:

Nuclear Engineering and Design

Année:

1988

Langue:

english

Fichier:

PDF, 1.04 MB

english, 1988

19

Mixed convection recirculation flow in a vertical single-rod channel connected to an upper plenum

Abdel-Raouf I. Barakat, Neil E. Todreas

Journal:

Nuclear Engineering and Design

Année:

1992

Langue:

english

Fichier:

PDF, 996 KB

english, 1992

20

Mixed convective flow penetration in vertical channels

Dong W. Jerng, Neil E. Todreas

Journal:

Nuclear Engineering and Design

Année:

1994

Langue:

english

Fichier:

PDF, 940 KB

english, 1994

21

Thermal Analysis of Pressurized Water Reactors: L.S. Tong and J. Weisman, 2nd Edn.

Neil E. Todreas

Journal:

International Journal of Multiphase Flow

Année:

1980

Langue:

english

Fichier:

PDF, 132 KB

english, 1980

22

Fuel performance analysis for PWR cores

Antonino Romano, Carter A. Shuffler, Hans D. Garkisch, Donald R. Olander, Neil E. Todreas

Journal:

Nuclear Engineering and Design

Année:

2009

Langue:

english

Fichier:

PDF, 1.01 MB

english, 2009

23

Lead-cooled flexible conversion ratio fast reactor

Anna Nikiforova, Pavel Hejzlar, Neil E. Todreas

Journal:

Nuclear Engineering and Design

Année:

2009

Langue:

english

Fichier:

PDF, 2.32 MB

english, 2009

24

Cross-comparison of fast reactor concepts with various coolants

Pavel Hejzlar, Neil E. Todreas, Eugene Shwageraus, Anna Nikiforova, Robert Petroski, Michael J. Driscoll

Journal:

Nuclear Engineering and Design

Année:

2009

Langue:

english

Fichier:

PDF, 1.29 MB

english, 2009

25

Flexible conversion fast reactors

Neil Todreas, Pavel Hejzlar, Yassin Hassan

Journal:

Nuclear Engineering and Design

Année:

2009

Langue:

english

Fichier:

PDF, 70 KB

english, 2009

26

Reliability analysis of a passive cooling system using a response surface with an application to the flexible conversion ratio reactor

Christopher J. Fong, George E. Apostolakis, Dustin R. Langewisch, Pavel Hejzlar, Neil E. Todreas, Michael J. Driscoll

Journal:

Nuclear Engineering and Design

Année:

2009

Langue:

english

Fichier:

PDF, 1.42 MB

english, 2009

27

Thermal hydraulic design of a liquid salt-cooled flexible conversion ratio fast reactor

Robert Petroski, Pavel Hejzlar, Neil E. Todreas

Journal:

Nuclear Engineering and Design

Année:

2009

Langue:

english

Fichier:

PDF, 2.69 MB

english, 2009

28

Flexible conversion ratio fast reactors: Overview

Neil E. Todreas, Pavel Hejzlar, Anna Nikiforova, Robert Petroski, Eugene Shwageraus, C.J. Fong, Michael J. Driscoll, M.A. Elliott, George Apostolakis

Journal:

Nuclear Engineering and Design

Année:

2009

Langue:

english

Fichier:

PDF, 627 KB

english, 2009

29

Core power limits for a lead-bismuth natural circulation actinide burner reactor

Cliff B. Davis, Dohyoung Kim, Neil E. Todreas, Mujid S. Kazimi

Journal:

Nuclear Engineering and Design

Année:

2002

Langue:

english

Fichier:

PDF, 342 KB

english, 2002

30

gothic code evaluation of alternative passive containment cooling features

Mirela Gavrilas, Pavel Hejzlar, Neil E. Todreas, Michael J. Driscoll

Journal:

Nuclear Engineering and Design

Année:

1996

Langue:

english

Fichier:

PDF, 1.21 MB

english, 1996

31

Flooding of a large, passive, pressure-tube light water reactor

Pavel Hejzlar, Neil E. Todreas, Michael J. Driscoll

Journal:

Nuclear Engineering and Design

Année:

1997

Langue:

english

Fichier:

PDF, 900 KB

english, 1997

32

The design and evaluation of a passively cooled containment for a high-rating pressurized water reactor

Mirela Gavrilas, Neil E Todreas, Michael J Driscoll

Journal:

Nuclear Engineering and Design

Année:

2000

Langue:

english

Fichier:

PDF, 947 KB

english, 2000

33

Containment passive-cooling design concepts

Mirela Gavrilas, Neil E. Todreas, Michael J. Driscoll

Journal:

Progress in Nuclear Energy

Année:

1998

Langue:

english

Fichier:

PDF, 669 KB

english, 1998

34

Expansion of the method of correlated temperatures to clad and fuel design analyses

Pedro Carajilescov, Neil E. Todreas

Journal:

Nuclear Engineering and Design

Année:

1974

Langue:

english

Fichier:

PDF, 1.00 MB

english, 1974

35

Thermal stress initiated fracture as a fragmentation mechanism in the UO2-sodium fuel-coolant interaction

Roland B. Knapp, Neil E. Todreas

Journal:

Nuclear Engineering and Design

Année:

1975

Langue:

english

Fichier:

PDF, 1.07 MB

english, 1975

36

Enthalpy transfer between PWR fuel assemblies in analysis by the lumped subchannel model

Chong Chiu, Pablo Moreno, Neil Todreas, Robert Bowring

Journal:

Nuclear Engineering and Design

Année:

1979

Langue:

english

Fichier:

PDF, 1.18 MB

english, 1979

37

Advanced fuel elements for passive pressure tube light water reactors

Pavel Hejzlar, Brett T. Mattingly, Neil E. Todreas, Michael J. Driscoll

Journal:

Nuclear Engineering and Design

Année:

1997

Langue:

english

Fichier:

PDF, 1.46 MB

english, 1997

38

Heat Transfer and Fluid Flow in Nuclear Systems || Pressurized Subcooled Light Water Systems

Todreas, Neil E.

Année:

1981

Langue:

english

Fichier:

PDF, 3.06 MB

english, 1981

39

[ASME 10th International Conference on Nuclear Engineering - Arlington, Virginia, USA (April 14–18, 2002)] 10th International Conference on Nuclear Engineering, Volume 2 - Design Strategies for Lead-Alloy-Cooled Reactors for Actinide Burning and Low-Cost Electricity Production

Hejzlar, Pavel, Todreas, Neil E., Driscoll, Michael J., MacDonald, Philip E., Buongiorno, Jacopo, Weaver, Kevan D.

Année:

2002

Langue:

english

Fichier:

PDF, 413 KB

english, 2002

40

[ASME ASME 2014 Small Modular Reactors Symposium - Washington, DC, USA (Tuesday 15 April 2014)] ASME 2014 Small Modular Reactors Symposium - Offshore Small Modular Reactor (OSMR): An Innovative Plant Design for Societally Acceptable and Economically Attractive Nuclear Energy in a Post-Fukushima, Post-9/11 World

Buongiorno, Jacopo, Golay, Michael, Todreas, Neil, Briccetti, Angelo, Jurewicz, Jake, Kindfuller, Vincent, Fadel, Daniel, Srinivasan, Ganesh, Hannink, Ryan, Crowle, Alan, Corradini, Michael

Année:

2014

Langue:

english

Fichier:

PDF, 1.38 MB

english, 2014

41

[ASME 10th International Conference on Nuclear Engineering - Arlington, Virginia, USA (April 14–18, 2002)] 10th International Conference on Nuclear Engineering, Volume 2 - A Supercritical CO

Dostal, Vaclav, Driscoll, Michael J., Hejzlar, Pavel, Todreas, Neil E.

Année:

2002

Langue:

english

Fichier:

PDF, 278 KB

english, 2002

42

N UCLEAR P OWER E CONOMIC P ERFORMANCE : Challenges and Opportunities

Kazimi, Mujid S., Todreas, Neil E.

Journal:

Annual Review of Energy and the Environment

Année:

1999

Langue:

english

Fichier:

PDF, 562 KB

english, 1999

43

[ASME 2016 24th International Conference on Nuclear Engineering - Charlotte, North Carolina, USA (Sunday 26 June 2016)] Volume 5: Student Paper Competition - Overview of Security Plan for Offshore Floating Nuclear Plant

Kindfuller, Vincent, Todreas, Neil, Buongiorno, Jacopo, Golay, Michael, Birch, Arthur, Isdanavich, Thomas, Thomas, Ron, Stevens, Harvey

Année:

2016

Langue:

english

Fichier:

PDF, 4.03 MB

english, 2016

44

Medium-Power Lead-Alloy Fast Reactor Balance-of-Plant Options

Dostal, Vaclav, Hejzlar, Pavel, Todreas, Neil E., Buongiorno, Jacopo

Journal:

Nuclear Technology

Année:

2004

Langue:

english

Fichier:

PDF, 651 KB

english, 2004

45

Fertile-Free Fast Lead-Cooled Incinerators for Efficient Actinide Burning

Romano, Antonino, Hejzlar, Pavel, Todreas, Neil E.

Journal:

Nuclear Technology

Année:

2004

Langue:

english

Fichier:

PDF, 845 KB

english, 2004

46

Effective Thermal Conductivity and Edge Conductance Model for a Spent-Fuel Assembly

Manteufel, Randall D., Todreas, Neil E.

Journal:

Nuclear Technology

Année:

1994

Langue:

english

Fichier:

PDF, 4.15 MB

english, 1994

47

Methodology for Characterizing Representativeness Uncertainty in Orifice Plate Mass Flow Rate Measurements Using CFD Simulations

Otgonbaatar, Uuganbayar, Baglietto, Emilio, Todreas, Neil

Journal:

Nuclear Science and Engineering

Année:

2016

Langue:

english

Fichier:

PDF, 4.01 MB

english, 2016

48

Medium-Power Lead-Alloy Reactors: Missions for This Reactor Technology

Todreas, Neil E., MacDonald, Philip E., Hejzlar, Pavel, Buongiorno, Jacopo, Loewen, Eric P.

Journal:

Nuclear Technology

Année:

2004

Langue:

english

Fichier:

PDF, 340 KB

english, 2004

49

Maintenance Cycle Extension in the IRIS Advanced Light Water Reactor Plant Design

Galvin, Mark R., Todreas, Neil E., Conway, Larry E.

Journal:

Nuclear Technology

Année:

2003

Langue:

english

Fichier:

PDF, 502 KB

english, 2003

50

Design Strategy and Constraints for Medium-Power Lead-Alloy–Cooled Actinide Burners

Hejzlar, Pavel, Buongiorno, Jacopo, MacDonald, Philip E., Todreas, Neil E.

Journal:

Nuclear Technology

Année:

2004

Langue:

english

Fichier:

PDF, 734 KB

english, 2004