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1

Experimental and Analytical Study of Axial Turbulent Flows in an Interior Subchannel of a Bare Rod Bundle

Carajilescov, P., Todreas, N. E.

Journal:

Journal of Heat Transfer

Year:

1976

Language:

english

File:

PDF, 555 KB

english, 1976

2

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

Year:

1986

Language:

english

File:

PDF, 1.45 MB

english, 1986

3

Letter to the editor on the paper by D.C. Groeneveld and L.K.H. Leung, “The 1995 look-up table for critical heat flux in tubes”

N.E. Todreas, P. Hejzlar

Journal:

Nuclear Engineering and Design

Year:

1996

Language:

english

File:

PDF, 118 KB

english, 1996

4

Thermal hydraulic analysis for grid supported pressurized water reactor cores

C. Shuffler, J. Trant, J. Malen, N. Todreas

Journal:

Nuclear Engineering and Design

Year:

2009

Language:

english

File:

PDF, 2.48 MB

english, 2009

5

Advanced Light-Water Reactors

Golay, Michael W., Todreas, Neil E.

Journal:

Scientific American

Year:

1990

Language:

english

File:

PDF, 879 KB

english, 1990

6

Handbook of Small Modular Nuclear Reactors || Small modular reactors (SMRs) for producing nuclear energy: an introduction

Year:

2015

Language:

english

File:

PDF, 672 KB

english, 2015

7

Thermal-Hydraulic Challenges in Fast Reactor Design

Todreas, Neil E.

Journal:

Nuclear Technology

Year:

2009

Language:

english

File:

PDF, 795 KB

english, 2009

8

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

Year:

2018

Language:

english

File:

PDF, 2.65 MB

english, 2018

9

Analytic formulae for the effective conductivity of a square or hexagonal array of parallel tubes

R.D. Manteufel, N.E. Todreas

Journal:

International Journal of Heat and Mass Transfer

Year:

1994

Language:

english

File:

PDF, 1011 KB

english, 1994

10

Advances in two-phase flow modeling for LMFBR applications

A.L. Schor, M.S. Kazimi, N.E. Todreas

Journal:

Nuclear Engineering and Design

Year:

1984

Language:

english

File:

PDF, 1.87 MB

english, 1984

11

Distributed resistance modeling of wire-wrapped rod bundles

Hisashi Ninokata, Apostolos Efthimiadis, Neil E. Todreas

Journal:

Nuclear Engineering and Design

Year:

1987

Language:

english

File:

PDF, 657 KB

english, 1987

12

Passive decay heat removal in advanced LWR concepts

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

Journal:

Nuclear Engineering and Design

Year:

1993

Language:

english

File:

PDF, 1.64 MB

english, 1993

13

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

Year:

1996

Language:

english

File:

PDF, 559 KB

english, 1996

14

Response of Hejzlar and Todreas to contributors' letters and technical notes

P. Hejzlar, N.E. Todreas

Journal:

Nuclear Engineering and Design

Year:

1996

Language:

english

File:

PDF, 474 KB

english, 1996

15

An assessment of two-phase pressure drop correlations for steam-water systems

W. Idsinga, N. Todreas, R. Bowring

Journal:

International Journal of Multiphase Flow

Year:

1977

Language:

english

File:

PDF, 710 KB

english, 1977

16

An experimental investigation of a passive cooling unit for nuclear plant containment

H. Liu, N.E. Todreas, M.J. Driscoll

Journal:

Nuclear Engineering and Design

Year:

2000

Language:

english

File:

PDF, 356 KB

english, 2000

17

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

Year:

1999

Language:

english

File:

PDF, 307 KB

english, 1999

18

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

Year:

1988

Language:

english

File:

PDF, 1.48 MB

english, 1988

19

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

Year:

2000

Language:

english

File:

PDF, 73 KB

english, 2000

20

Construction of a fine wire thermocouple capable of repeated insertions into and accurate positioning within a controlled environmental chamber

L. Battist, F. Goldner, N. Todreas

Journal:

Medical and Biological Engineering and Computing

Year:

1969

Language:

english

File:

PDF, 614 KB

english, 1969

21

Numerical implementation of the Cheng and Todreas correlation for wire wrapped bundle friction factors-desirable improvements in the transition flow region

Chen, S.K., Petroski, R., Todreas, N.E.

Journal:

Nuclear Engineering and Design

Year:

2013

Language:

english

File:

PDF, 649 KB

english, 2013

22

Buoyancy and Property Variation Effects in Turbulent Mixed Convection of Water in Vertical Tubes

Parlatan, Y., Todreas, N. E., Driscoll, M. J.

Journal:

Journal of Heat Transfer

Year:

1996

Language:

english

File:

PDF, 2.15 MB

english, 1996

23

Turbulence Modeling of Axial Flow in a Bare Rod Bundle

Bartzis, J. G., Todreas, N. E.

Journal:

Journal of Heat Transfer

Year:

1979

Language:

english

File:

PDF, 664 KB

english, 1979

24

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

Year:

2016

Language:

english

File:

PDF, 1.94 MB

english, 2016

25

The Offshore Floating Nuclear Plant Concept

Buongiorno, J., Jurewicz, J., Golay, M., Todreas, N.

Journal:

Nuclear Technology

Year:

2016

Language:

english

File:

PDF, 2.89 MB

english, 2016

26

Thermal Contact Conductance in Reactor Fuel Elements

Jacobs, Gary, Todreas, Neil

Journal:

Nuclear Science and Engineering

Year:

1973

Language:

english

File:

PDF, 1.03 MB

english, 1973

27

Design and Economic Evaluation of an Advanced Tight-Lattice Core for the IRIS Integral Primary System Reactor

Saccheri, J. G. B., Todreas, N. E., Driscoll, M. J.

Journal:

Nuclear Technology

Year:

2007

Language:

english

File:

PDF, 1.16 MB

english, 2007

28

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

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

Journal:

Nuclear Technology

Year:

1980

Language:

english

File:

PDF, 1.01 MB

english, 1980

29

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

Year:

1974

Language:

english

File:

PDF, 1.29 MB

english, 1974

30

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

Year:

1975

Language:

english

File:

PDF, 1002 KB

english, 1975

31

A porous body model for predicting temperature distribution in wire-wrapped fuel rod assemblies

E.U. Khan, W.M. Rohsenow, A.A. Sonin, N.E. Todreas

Journal:

Nuclear Engineering and Design

Year:

1975

Language:

english

File:

PDF, 720 KB

english, 1975

32

Steady state thermal analysis of PWRs by a single-pass procedure using a simplified nodal layout

P. Moreno, J. Liu, E. Khan, N. Todreas

Journal:

Nuclear Engineering and Design

Year:

1978

Language:

english

File:

PDF, 902 KB

english, 1978

33

Prediction of minimum UO2 particle size based on thermal stress initiated fracture model

M. Corradini, N.E. Todreas

Journal:

Nuclear Engineering and Design

Year:

1979

Language:

english

File:

PDF, 836 KB

english, 1979

34

Formulation of the fluid-solid interaction force for multi-dimensional, two-phase flow within tube arrays

Y. Coëffé, N. Todreas

Journal:

Nuclear Engineering and Design

Year:

1980

Language:

english

File:

PDF, 513 KB

english, 1980

35

Natural circulation of electrically conducting liquids in fusion reactor blankets

P.J. Gierszewski, B. Mikic, N.E. Todreas

Journal:

Nuclear Engineering and Design

Year:

1982

Language:

english

File:

PDF, 636 KB

english, 1982

36

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

Year:

1986

Language:

english

File:

PDF, 719 KB

english, 1986

37

Foreword

Neil E. Todreas, Chong Chiu

Journal:

Nuclear Engineering and Design

Year:

1987

Language:

english

File:

PDF, 50 KB

english, 1987

38

Energy transfer mechanisms in LMR rod bundles under mixed convection conditions

Tae Sun Ro, Neil E. Todreas

Journal:

Nuclear Engineering and Design

Year:

1988

Language:

english

File:

PDF, 1.04 MB

english, 1988

39

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

Year:

1992

Language:

english

File:

PDF, 996 KB

english, 1992

40

Mixed convective flow penetration in vertical channels

Dong W. Jerng, Neil E. Todreas

Journal:

Nuclear Engineering and Design

Year:

1994

Language:

english

File:

PDF, 940 KB

english, 1994

41

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

Neil E. Todreas

Journal:

International Journal of Multiphase Flow

Year:

1980

Language:

english

File:

PDF, 132 KB

english, 1980

42

Void distributions in bubbly flow through yawed rod arrays

J.T. Robinson, N.E. Todreas, D. Ebeling-Koning

Journal:

International Journal of Multiphase Flow

Year:

1988

Language:

english

File:

PDF, 975 KB

english, 1988

43

The design and safety features of the IRIS reactor

Mario D. Carelli, L.E. Conway, L. Oriani, B. Petrović, C.V. Lombardi, M.E. Ricotti, A.C.O. Barroso, J.M. Collado, L. Cinotti, N.E. Todreas, D. Grgić, M.M. Moraes, R.D. Boroughs, H. Ninokata, D.T. Inge

Journal:

Nuclear Engineering and Design

Year:

2004

Language:

english

File:

PDF, 557 KB

english, 2004

44

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

Year:

2009

Language:

english

File:

PDF, 1.01 MB

english, 2009

45

Hydride fuel for LWRs—Project overview

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

Journal:

Nuclear Engineering and Design

Year:

2009

Language:

english

File:

PDF, 4.90 MB

english, 2009

46

Steady state thermal-hydraulic analysis of hydride-fueled grid-supported BWRs

P. Ferroni, C.S. Handwerk, N.E. Todreas

Journal:

Nuclear Engineering and Design

Year:

2009

Language:

english

File:

PDF, 1.95 MB

english, 2009

47

Thermal-hydraulic analysis for wire-wrapped PWR cores

P. Diller, N. Todreas, P. Hejzlar

Journal:

Nuclear Engineering and Design

Year:

2009

Language:

english

File:

PDF, 1.67 MB

english, 2009

48

Economic analysis of grid and wire wrap supported hydride and oxide fueled pressurized water reactors

C. Shuffler, P. Diller, J. Malen, N. Todreas, E. Greenspan, B. Petrovic

Journal:

Nuclear Engineering and Design

Year:

2009

Language:

english

File:

PDF, 3.81 MB

english, 2009

49

Thermal hydraulic design of a hydride-fueled inverted PWR core

J.A. Malen, N.E. Todreas, P. Hejzlar, P. Ferroni, A. Bergles

Journal:

Nuclear Engineering and Design

Year:

2009

Language:

english

File:

PDF, 867 KB

english, 2009

50

Economic analysis of hydride fueled BWR

F. Ganda, C. Shuffler, E. Greenspan, N. Todreas

Journal:

Nuclear Engineering and Design

Year:

2009

Language:

english

File:

PDF, 281 KB

english, 2009

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