Todreas, N.: search on Z-Library

The world's largest scientific articles store. 70,000,000+ articles for free.

Don't use scam websites

51

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

Year:

2009

Language:

english

File:

PDF, 1.29 MB

english, 2009

52

Lead-cooled flexible conversion ratio fast reactor

Anna Nikiforova, Pavel Hejzlar, Neil E. Todreas

Journal:

Nuclear Engineering and Design

Year:

2009

Language:

english

File:

PDF, 2.32 MB

english, 2009

53

Flexible conversion fast reactors

Neil Todreas, Pavel Hejzlar, Yassin Hassan

Journal:

Nuclear Engineering and Design

Year:

2009

Language:

english

File:

PDF, 70 KB

english, 2009

54

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

Year:

2009

Language:

english

File:

PDF, 1.42 MB

english, 2009

55

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

Year:

2009

Language:

english

File:

PDF, 2.69 MB

english, 2009

56

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

Year:

2009

Language:

english

File:

PDF, 627 KB

english, 2009

57

Conceptual design and analysis of a semi-passive containment cooling system for a large concrete containment

C.S. Byun, D.W. Jerng, N.E. Todreas, M.J. Driscoll

Journal:

Nuclear Engineering and Design

Year:

2000

Language:

english

File:

PDF, 253 KB

english, 2000

58

Erratum to “Conceptual design and analysis of a semi-passive containment cooling system for a large concrete containment”: [Nucl. Eng. Des. 199 (2000) 227–242]

C.S. Byun, D.W. Jerng, N.E. Todreas, M.J. Driscoll

Journal:

Nuclear Engineering and Design

Year:

2001

Language:

english

File:

PDF, 40 KB

english, 2001

59

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

Year:

2002

Language:

english

File:

PDF, 342 KB

english, 2002

60

gothic code evaluation of alternative passive containment cooling features

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

Journal:

Nuclear Engineering and Design

Year:

1996

Language:

english

File:

PDF, 1.21 MB

english, 1996

61

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

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

Journal:

Nuclear Engineering and Design

Year:

1997

Language:

english

File:

PDF, 900 KB

english, 1997

62

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

Year:

2000

Language:

english

File:

PDF, 947 KB

english, 2000

63

Containment passive-cooling design concepts

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

Journal:

Progress in Nuclear Energy

Year:

1998

Language:

english

File:

PDF, 669 KB

english, 1998

64

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

Pedro Carajilescov, Neil E. Todreas

Journal:

Nuclear Engineering and Design

Year:

1974

Language:

english

File:

PDF, 1.00 MB

english, 1974

65

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

Year:

1975

Language:

english

File:

PDF, 1.07 MB

english, 1975

66

A porous body model for predicting temperature distribution in wire-wrapped rod assemblies operating in combined forced and free convection

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

Journal:

Nuclear Engineering and Design

Year:

1975

Language:

english

File:

PDF, 769 KB

english, 1975

67

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

Year:

1979

Language:

english

File:

PDF, 1.18 MB

english, 1979

68

Experimental techniques for liquid metal cooled fast breeder reactor fuel assembly thermal/hydraulic tests

C. Chiu, N. Todreas, R. Morris

Journal:

Nuclear Engineering and Design

Year:

1980

Language:

english

File:

PDF, 1.28 MB

english, 1980

69

Hydraulic characteristics of wire-wrapped rod bundles

A.A. Bishop, N. Todreas

Journal:

Nuclear Engineering and Design

Year:

1980

Language:

english

File:

PDF, 1.29 MB

english, 1980

70

An approximate method for predicting temperature distribution in wire wrapped fuel assemblies of a liquid metal fast breeder reactor

B.B. Mikic, E.U. Kahn, N.E. Todreas

Journal:

Mechanics Research Communications

Year:

1976

Language:

english

File:

PDF, 355 KB

english, 1976

71

Experimental evaluation of pressure drop in round tubes provided with physically separated, multiple, short-length twisted tapes

P. Ferroni, R.E. Block, N.E. Todreas, A.E. Bergles

Journal:

Experimental Thermal and Fluid Science

Year:

2011

Language:

english

File:

PDF, 1.62 MB

english, 2011

72

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

Year:

1997

Language:

english

File:

PDF, 1.46 MB

english, 1997

73

A performance comparison of lithium, helium, and flibe cooled tube/header fusion blankets

J. Chao, P. Gierszewski, B. B. Mikic, N. E. Todreas, T. J. McManamy

Journal:

Journal of Fusion Energy

Year:

1982

Language:

english

File:

PDF, 1.11 MB

english, 1982

74

Evaluation of existing correlations for the prediction of pressure drop in wire-wrapped hexagonal array pin bundles

Chen, S.K., Todreas, N.E., Nguyen, N.T.

Journal:

Nuclear Engineering and Design

Year:

2014

Language:

english

File:

PDF, 3.51 MB

english, 2014

75

Critical heat flux and pressure drop for tubes containing multiple short-length twisted-tape swirl promoters

Arment, T.W., Todreas, N.E., Bergles, A.E.

Journal:

Nuclear Engineering and Design

Year:

2013

Language:

english

File:

PDF, 1.05 MB

english, 2013

76

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

Todreas, Neil E.

Year:

1981

Language:

english

File:

PDF, 3.06 MB

english, 1981

77

Criteria for the Onset of Flow Recirculation and Onset of Mixed Convection in Vertical Rod Bundles

Symolon, P. D., Todreas, N. E., Rohsenow, W. M.

Journal:

Journal of Heat Transfer

Year:

1987

Language:

english

File:

PDF, 834 KB

english, 1987

78

Heat Transfer Correlation for Reactor Riser in Mixed Convection Air Flow

Fu, G., Todreas, N. E., Hejzlar, P., Driscoll, M. J.

Journal:

Journal of Heat Transfer

Year:

1994

Language:

english

File:

PDF, 470 KB

english, 1994

79

Experimental Investigation of Flow Resistance and Wall Shear Stress in the Interior Subchannel of a Triangular Array of Parallel Rods

Fakory, M., Todreas, N.

Journal:

Journal of Fluids Engineering

Year:

1979

Language:

english

File:

PDF, 611 KB

english, 1979

80

[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.

Year:

2002

Language:

english

File:

PDF, 413 KB

english, 2002

81

[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

Year:

2014

Language:

english

File:

PDF, 1.38 MB

english, 2014

82

[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.

Year:

2002

Language:

english

File:

PDF, 278 KB

english, 2002

83

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

Year:

1999

Language:

english

File:

PDF, 562 KB

english, 1999

84

[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

Year:

2016

Language:

english

File:

PDF, 4.03 MB

english, 2016

85

Mixed Convective Low Flow Pressure Drop in Vertical Rod Assemblies: I—Predictive Model and Design Correlation

Suh, K. Y., Todreas, N. E., Rohsenow, W. M.

Journal:

Journal of Heat Transfer

Year:

1989

Language:

english

File:

PDF, 1.59 MB

english, 1989

86

Heavy-Metal Aerosol Transport in a Lead-Bismuth-Cooled Fast Reactor with In-Vessel Direct-Contact Steam Generation

Buongiorno, J., Todreas, N. E., Kazimi, M. S.

Journal:

Nuclear Technology

Year:

2002

Language:

english

File:

PDF, 392 KB

english, 2002

87

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

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

Journal:

Nuclear Technology

Year:

2004

Language:

english

File:

PDF, 651 KB

english, 2004

88

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

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

Journal:

Nuclear Technology

Year:

2004

Language:

english

File:

PDF, 845 KB

english, 2004

89

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

Manteufel, Randall D., Todreas, Neil E.

Journal:

Nuclear Technology

Year:

1994

Language:

english

File:

PDF, 4.15 MB

english, 1994

90

Mixed Convective Low Flow Pressure Drop in Vertical Rod Assemblies: II—Experimental Validation

Suh, K. Y., Todreas, N. E., Rohsenow, W. M.

Journal:

Journal of Heat Transfer

Year:

1989

Language:

english

File:

PDF, 798 KB

english, 1989

91

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

Year:

2016

Language:

english

File:

PDF, 4.01 MB

english, 2016

92

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

Year:

2004

Language:

english

File:

PDF, 340 KB

english, 2004

93

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

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

Journal:

Nuclear Technology

Year:

2003

Language:

english

File:

PDF, 502 KB

english, 2003

94

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

Year:

2004

Language:

english

File:

PDF, 734 KB

english, 2004

95

A Methodology for Selecting High Thermal-Hydraulic Performance Fuel Configurations for Tightly Packed Epithermal Core Designs

Romano, Antonino, Todreas, Neil E.

Journal:

Nuclear Technology

Year:

2002

Language:

english

File:

PDF, 279 KB

english, 2002

96

Reload Light Water Reactor Core Designs for an Ultralong Operating Cycle

McMahon, Michael V., Driscoll, Michael J., Pilat, Edward E., Todreas, Neil E.

Journal:

Nuclear Technology

Year:

1999

Language:

english

File:

PDF, 1.18 MB

english, 1999

97

Interchannel Mixing in Wire Wrapped Liquid Metal Fast Reactor Fuel Assemblies

Todreas, Neil E., Turi, James A.

Journal:

Nuclear Technology

Year:

1972

Language:

english

File:

PDF, 1.56 MB

english, 1972

98

An Experimental Correlation of Cross-Flow Pressure Drop for Triangular Array Wire-Wrapped Rod Assemblies

Yull Suh, Kune, Todreas, Neil E.

Journal:

Nuclear Technology

Year:

1987

Language:

english

File:

PDF, 2.75 MB

english, 1987

99

Conceptual Design Features for a Passive Light Water Cooled and Moderated Pressure Tube Reactor (PLPTR)

Tang, Jan Ru, Todreas, Neil E., Driscoll, Michael J.

Journal:

Nuclear Technology

Year:

1994

Language:

english

File:

PDF, 3.76 MB

english, 1994

100

Large Passive Pressure Tube Light Water Reactor with Voided Calandria

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

Journal:

Nuclear Technology

Year:

1996

Language:

english

File:

PDF, 6.33 MB

english, 1996