Page 1 | Search Results | J. Fluids Eng.

1-20 of 39

Sort by

Sort Order Select

Journal Articles

Radioactive Cutting Tools for Rapid Tool-Life Testing

M. E. Merchant, Hans Ernst, E. J. Krabacher

Publisher: ASME

J. Fluids Eng. May 1953, 75(4): 549–559.

https://doi.org/10.1115/1.4015354

Published Online: July 29, 2022

View Article titled, Radioactive Cutting Tools for Rapid Tool-Life Testing

Topics: Cutting tools, Testing, Cutting, Wear, Fluids, Irradiation (Radiation exposure), Machining, Neutrons, Nuclear reactors, Particulate matter

Journal Articles

Apparatus for Study of Effects of Cyclic Thermal Stresses on Ductile Metals

L. F. Coffin, Jr., R. P. Wesley

Publisher: ASME

J. Fluids Eng. August 1954, 76(6): 923–930.

https://doi.org/10.1115/1.4015019

Published Online: July 1, 2022

View Article titled, Apparatus for Study of Effects of Cyclic Thermal Stresses on Ductile Metals

Topics: Metals, Thermal stresses, Fatigue, Stress, Cycles, Damage, Deformation, Fatigue failure, Heat transfer, Nickel

Journal Articles

Discussion: “The Thermal Design of Nuclear Power Reactors” (Palladino, N. J., 1955, Trans. ASME, 77, pp. 667–673)

Alfred Amorosi

Publisher: ASME

J. Fluids Eng. July 1955, 77(5): 673.

https://doi.org/10.1115/1.4014462

Published Online: July 1, 2022

View Article titled, Discussion: “The Thermal Design of Nuclear Power Reactors” (Palladino, N. J., 1955, Trans. ASME, 77, pp. 667–673)

Topics: Design, Nuclear reactors

Journal Articles

The Thermal Design of Nuclear Power Reactors

N. J. Palladino

Publisher: ASME

J. Fluids Eng. July 1955, 77(5): 667–673.

https://doi.org/10.1115/1.4014461

Published Online: July 1, 2022

View Article titled, The Thermal Design of Nuclear Power Reactors

Topics: Design, Nuclear reactors, Temperature, Heat, Metal surfaces, Boiling, Coolants, Corrosion, Flow (Dynamics), Fuels

Journal Articles

Power Removal from Boiling Nuclear Reactors

P. C. Zmola, R. V. Bailey

Publisher: ASME

J. Fluids Eng. May 1956, 78(4): 881–892.

https://doi.org/10.1115/1.4013860

Published Online: February 21, 2022

View Article titled, Power Removal from Boiling Nuclear Reactors

Topics: Boiling, Nuclear reactors, Coolants, Density, Electrical resistance, Fluid density, Fuels, Heating, Power density, Vapors

Journal Articles

Use of Numerical Analysis in the Transient Solution of Two-Dimensional Heat-Transfer Problem With Natural and Forced Convection

S. K. Hellman, George Habetler, Harold Babrov

Publisher: ASME

J. Fluids Eng. August 1956, 78(6): 1155–1161.

https://doi.org/10.1115/1.4013965

Published Online: February 21, 2022

View Article titled, Use of Numerical Analysis in the Transient Solution of Two-Dimensional Heat-Transfer Problem With Natural and Forced Convection

Topics: Heat transfer, Mixed convection, Numerical analysis, Transients (Dynamics), Flow (Dynamics), Computers, Cooling, Heat, Heat conduction, Liquid metals

Journal Articles

Evaluation of the Nonlinear Kinetic Behavior of a Nuclear Power Reactor

R. C. Howard

Publisher: ASME

J. Fluids Eng. January 1956, 78(1): 163–169.

https://doi.org/10.1115/1.4013602

Published Online: February 21, 2022

View Article titled, Evaluation of the Nonlinear Kinetic Behavior of a Nuclear Power Reactor

Topics: Nuclear reactors, Transients (Dynamics), Analytical methods, Computers, Errors, Graphite, Heat exchangers, Sodium, Stability

Journal Articles

Methods of Refueling Heterogeneous Nuclear Reactors

Stuart McLain, A. H. Barnes, R. C. Goertz

Publisher: ASME

J. Fluids Eng. January 1957, 79(1): 47–53.

https://doi.org/10.1115/1.4012918

Published Online: February 14, 2022

View Article titled, Methods of Refueling Heterogeneous Nuclear Reactors

Topics: Nuclear reactors

Journal Articles

Heat-Transfer and Flow-Friction Characteristics of Woven-Screen and Crossed-Rod Matrixes

L. S. Tong, A. L. London

Publisher: ASME

J. Fluids Eng. October 1957, 79(7): 1558–1570.

https://doi.org/10.1115/1.4013401

Published Online: February 14, 2022

View Article titled, Heat-Transfer and Flow-Friction Characteristics of Woven-Screen and Crossed-Rod Matrixes

Topics: Flow (Dynamics), Friction, Heat transfer, Algebra, Design, Fuels, Interpolation, Mass transfer, Nuclear reactors, Reynolds number

Journal Articles

Fuel Elements for Nuclear Reactors

J. B. Anderson

Publisher: ASME

J. Fluids Eng. January 1957, 79(1): 29–33.

https://doi.org/10.1115/1.4012915

Published Online: February 14, 2022

View Article titled, Fuel Elements for Nuclear Reactors

Topics: Fuels, Nuclear reactors, Heat transfer, Design

Journal Articles

Local Laminar Heat Transfer in Wedge-Shaped Passages

E. R. G. Eckert, T. F. Irvine, Jr., J. T. Yen

Publisher: ASME

J. Fluids Eng. October 1958, 80(7): 1433–1438.

https://doi.org/10.1115/1.4012749

Published Online: January 25, 2022

View Article titled, Local Laminar Heat Transfer in Wedge-Shaped Passages

Topics: Heat transfer, Wedges, Heat flux, Temperature, Boundary-value problems, Ducts, Cross section (Physics), Engineering systems and industry applications, Flow (Dynamics), Friction

Journal Articles

Treatment of Make-Up Feedwater, Condensate, and Recycle Water for Supercritical and Nuclear-Reactor Power-Plant Cycles

V. J. Calise, J. H. Duff

Publisher: ASME

J. Fluids Eng. November 1958, 80(8): 1659–1672.

https://doi.org/10.1115/1.4012842

Published Online: January 25, 2022

View Article titled, Treatment of Make-Up Feedwater, Condensate, and Recycle Water for Supercritical and Nuclear-Reactor Power-Plant Cycles

Topics: Condensed matter, Cycles, Feedwater, Nuclear reactors, Power stations, Water, Nuclear power stations, Water treatment

Journal Articles

Discussion: “Treatment of Make-Up Feedwater, Condensate, and Recycle Water for Supercritical and Nuclear-Reactor Power-Plant Cycles” (Calise, V. J., and Duff, J. H., 1958, Trans. ASME, 80, pp. 1659–1672)

J. H. Harlow

Publisher: ASME

J. Fluids Eng. November 1958, 80(8): 1674.

https://doi.org/10.1115/1.4012846

Published Online: January 25, 2022

View Article titled, Discussion: “Treatment of Make-Up Feedwater, Condensate, and Recycle Water for Supercritical and Nuclear-Reactor Power-Plant Cycles” (Calise, V. J., and Duff, J. H., 1958, Trans. ASME, 80, pp. 1659–1672)

Topics: Condensed matter, Cycles, Feedwater, Nuclear reactors, Power stations, Water

Journal Articles

Discussion: “Treatment of Make-Up Feedwater, Condensate, and Recycle Water for Supercritical and Nuclear-Reactor Power-Plant Cycles” (Calise, V. J., and Duff, J. H., 1958, Trans. ASME, 80, pp. 1659–1672)

S. B. Applebaum

Publisher: ASME

J. Fluids Eng. November 1958, 80(8): 1672–1673.

https://doi.org/10.1115/1.4012843

Published Online: January 25, 2022

Topics: Condensed matter, Cycles, Feedwater, Nuclear reactors, Power stations, Water

Journal Articles

Discussion: “Treatment of Make-Up Feedwater, Condensate, and Recycle Water for Supercritical and Nuclear-Reactor Power-Plant Cycles” (Calise, V. J., and Duff, J. H., 1958, Trans. ASME, 80, pp. 1659–1672)

I. B. Dick

Publisher: ASME

J. Fluids Eng. November 1958, 80(8): 1673–1674.

https://doi.org/10.1115/1.4012845

Published Online: January 25, 2022

Topics: Condensed matter, Cycles, Feedwater, Nuclear reactors, Power stations, Water

Journal Articles

Discussion: “Treatment of Make-Up Feedwater, Condensate, and Recycle Water for Supercritical and Nuclear-Reactor Power-Plant Cycles” (Calise, V. J., and Duff, J. H., 1958, Trans. ASME, 80, pp. 1659–1672)

H. J. Vyhnalek, R. B. Shumaker

Publisher: ASME

J. Fluids Eng. November 1958, 80(8): 1675.

https://doi.org/10.1115/1.4012847

Published Online: January 25, 2022

Topics: Condensed matter, Cycles, Feedwater, Nuclear reactors, Power stations, Water

Journal Articles

Discussion: “Treatment of Make-Up Feedwater, Condensate, and Recycle Water for Supercritical and Nuclear-Reactor Power-Plant Cycles” (Calise, V. J., and Duff, J. H., 1958, Trans. ASME, 80, pp. 1659–1672)

Hilary E. Bacon

Publisher: ASME

J. Fluids Eng. November 1958, 80(8): 1673.

https://doi.org/10.1115/1.4012844

Published Online: January 25, 2022

Topics: Condensed matter, Cycles, Feedwater, Nuclear reactors, Power stations, Water

Journal Articles

Dynamic Response of Heat Exchangers Having Internal Heat Sources—Part I

J. A. Clark, V. S. Arpaci, K. M. Treadwell

Publisher: ASME

J. Fluids Eng. April 1958, 80(3): 612–622.

https://doi.org/10.1115/1.4012453

Published Online: January 25, 2022

View Article titled, Dynamic Response of Heat Exchangers Having Internal Heat Sources—Part I

Topics: Dynamic response, Heat, Heat exchangers, Coolants, Laplace transforms, Nuclear reactors, Spacetime, Temperature

Journal Articles

Dynamic Response of Heat Exchangers Having Internal Heat Sources—Part II

V. S. Arpaci, J. A. Clark

Publisher: ASME

J. Fluids Eng. April 1958, 80(3): 625–633.

https://doi.org/10.1115/1.4012457

Published Online: January 25, 2022

View Article titled, Dynamic Response of Heat Exchangers Having Internal Heat Sources—Part II

Topics: Dynamic response, Heat, Heat exchangers, Temperature, Differential equations, Fluids, Heat transfer, Machinery, Nuclear reactors, Spacetime

Journal Articles

Vibration of Rods Induced by Water in Parallel Flow

D. Burgreen, J. J. Byrnes, D. M. Benforado

Publisher: ASME

J. Fluids Eng. July 1958, 80(5): 991–1001.

https://doi.org/10.1115/1.4012582

Published Online: January 25, 2022

View Article titled, Vibration of Rods Induced by Water in Parallel Flow

Topics: Flow (Dynamics), Rods, Vibration, Water, Aluminum, Brass (Metal), Cycles, Fuel rods, Nuclear reactors, Temperature

Journal citation

NARROW

Radioactive Cutting Tools for Rapid Tool-Life Testing

Apparatus for Study of Effects of Cyclic Thermal Stresses on Ductile Metals

Discussion: “The Thermal Design of Nuclear Power Reactors” (Palladino, N. J., 1955, Trans. ASME, 77, pp. 667–673)

The Thermal Design of Nuclear Power Reactors

Power Removal from Boiling Nuclear Reactors

Use of Numerical Analysis in the Transient Solution of Two-Dimensional Heat-Transfer Problem With Natural and Forced Convection

Evaluation of the Nonlinear Kinetic Behavior of a Nuclear Power Reactor

Methods of Refueling Heterogeneous Nuclear Reactors

Heat-Transfer and Flow-Friction Characteristics of Woven-Screen and Crossed-Rod Matrixes

Fuel Elements for Nuclear Reactors

Local Laminar Heat Transfer in Wedge-Shaped Passages

Treatment of Make-Up Feedwater, Condensate, and Recycle Water for Supercritical and Nuclear-Reactor Power-Plant Cycles

Discussion: “Treatment of Make-Up Feedwater, Condensate, and Recycle Water for Supercritical and Nuclear-Reactor Power-Plant Cycles” (Calise, V. J., and Duff, J. H., 1958, Trans. ASME, 80, pp. 1659–1672)

Discussion: “Treatment of Make-Up Feedwater, Condensate, and Recycle Water for Supercritical and Nuclear-Reactor Power-Plant Cycles” (Calise, V. J., and Duff, J. H., 1958, Trans. ASME, 80, pp. 1659–1672)

Discussion: “Treatment of Make-Up Feedwater, Condensate, and Recycle Water for Supercritical and Nuclear-Reactor Power-Plant Cycles” (Calise, V. J., and Duff, J. H., 1958, Trans. ASME, 80, pp. 1659–1672)

Discussion: “Treatment of Make-Up Feedwater, Condensate, and Recycle Water for Supercritical and Nuclear-Reactor Power-Plant Cycles” (Calise, V. J., and Duff, J. H., 1958, Trans. ASME, 80, pp. 1659–1672)

Discussion: “Treatment of Make-Up Feedwater, Condensate, and Recycle Water for Supercritical and Nuclear-Reactor Power-Plant Cycles” (Calise, V. J., and Duff, J. H., 1958, Trans. ASME, 80, pp. 1659–1672)

Dynamic Response of Heat Exchangers Having Internal Heat Sources—Part I

Dynamic Response of Heat Exchangers Having Internal Heat Sources—Part II

Vibration of Rods Induced by Water in Parallel Flow

ASME Journals

ASME Conference Proceedings

ASME eBooks

Resources

Opportunities

ASME Journals

ASME Conference Proceedings

ASME eBooks

Resources

Opportunities

This Feature Is Available To Subscribers Only