Page 1 | Search Results | J. Fluids Eng.

1-9 of 9

Sort by

Sort Order Select

Journal Articles

Fracture Safety Analysis Concepts for Nuclear Pressure Vessels, Considering the Effects of Irradiation

J. G. Merkle

Publisher: ASME

J. Fluids Eng. June 1971, 93(2): 265–273.

https://doi.org/10.1115/1.3425223

Published Online: June 1, 1971

View Article titled, Fracture Safety Analysis Concepts for Nuclear Pressure Vessels, Considering the Effects of Irradiation

Topics: Fracture (Materials), Fracture (Process), Irradiation (Radiation exposure), Reactor vessels, Safety, Pressure vessels, Reliability, Temperature, Fluence (Radiation measurement), Fracture mechanics

Journal Articles

A Reassessment of Fracture-Safe Operating Criteria for Reactor Vessel Steels Based on Charpy-V Performance

F. J. Loss, J. R. Hawthorne, C. Z. Serpan, Jr.

Publisher: ASME

J. Fluids Eng. June 1971, 93(2): 247–258.

https://doi.org/10.1115/1.3425221

Published Online: June 1, 1971

View Article titled, A Reassessment of Fracture-Safe Operating Criteria for Reactor Vessel Steels Based on Charpy-V Performance

Topics: Fracture (Materials), Fracture (Process), Reactor vessels, Steel, Degrees of freedom, Fracture toughness, Vessels, Brittle fracture, Irradiation (Radiation exposure), Neutrons

Journal Articles

Use of Fracture Mechanics in Reactor Vessel Surveillance

T. R. Mager, S. E. Yanichko

Publisher: ASME

J. Fluids Eng. June 1971, 93(2): 259–264.

https://doi.org/10.1115/1.3425222

Published Online: June 1, 1971

View Article titled, Use of Fracture Mechanics in Reactor Vessel Surveillance

Topics: Fracture mechanics, Reactor vessels, Surveillance, Safety

Journal Articles

Yankee Reactor Pressure Vessel Surveillance: Notch Ductility Performance of Vessel Steel and Maximum Service Fluence Determined From Exposure During Cores II, III, and IV

C. Z. Serpan, Jr., J. R. Hawthorne

Publisher: ASME

J. Fluids Eng. December 1967, 89(4): 897–910.

https://doi.org/10.1115/1.3609735

Published Online: December 1, 1967

View Article titled, Yankee Reactor Pressure Vessel Surveillance: Notch Ductility Performance of Vessel Steel and Maximum Service Fluence Determined From Exposure During Cores II, III, and IV

Topics: Ductility, Fluence (Radiation measurement), Reactor vessels, Steel, Surveillance, Vessels, Embrittlement, Heat, Neutrons, Computation

Journal Articles

Features and Results of Several Programs of Radiation-Damage Surveillance of Power Reactor Pressure Vessels

Charles Z. Serpan, Jr., L. E. Steele, J. R. Hawthorne

Publisher: ASME

J. Fluids Eng. March 1967, 89(1): 221–232.

https://doi.org/10.1115/1.3609556

Published Online: March 1, 1967

View Article titled, Features and Results of Several Programs of Radiation-Damage Surveillance of Power Reactor Pressure Vessels

Topics: Radiation damage, Reactor vessels, Surveillance, Army, ASTM International, Rocks, Testing

Journal Articles

Reactor-Vessel Design Considering Radiation Effects

L. Porse

Publisher: ASME

J. Fluids Eng. December 1964, 86(4): 743–748.

https://doi.org/10.1115/1.3655941

Published Online: December 1, 1964

View Article titled, Reactor-Vessel Design Considering Radiation Effects

Topics: Design, Radiation effects, Reactor vessels, Temperature, Cycles, Irradiation (Radiation exposure), Metals, Neutrons, Pressure, Pressurized water reactors

Journal Articles

Discussion: “Reactor-Vessel Design Considering Radiation Effects” (Porse, L., 1964, ASME J. Basic Eng., 86, pp. 743–748)

N. J. Palladino

Publisher: ASME

J. Fluids Eng. December 1964, 86(4): 748.

https://doi.org/10.1115/1.3655942

Published Online: December 1, 1964

View Article titled, Discussion: “Reactor-Vessel Design Considering Radiation Effects” (Porse, L., 1964, ASME J. Basic Eng., 86, pp. 743–748)

Topics: Design, Radiation effects, Reactor vessels

Journal Articles

Discussion: “Reactor-Vessel Design Considering Radiation Effects” (Porse, L., 1964, ASME J. Basic Eng., 86, pp. 743–748)

D. W. Sher

Publisher: ASME

J. Fluids Eng. December 1964, 86(4): 748–749.

https://doi.org/10.1115/1.3655943

Published Online: December 1, 1964

View Article titled, Discussion: “Reactor-Vessel Design Considering Radiation Effects” (Porse, L., 1964, ASME J. Basic Eng., 86, pp. 743–748)

Topics: Design, Radiation effects, Reactor vessels

Journal Articles

Closure to “Discussions of ‘Reactor-Vessel Design Considering Radiation Effects’” (1964, ASME J. Basic Eng., 86, pp. 748–749)

L. Porse

Publisher: ASME

J. Fluids Eng. December 1964, 86(4): 749.

https://doi.org/10.1115/1.3655944

Published Online: December 1, 1964

View Article titled, Closure to “Discussions of ‘Reactor-Vessel Design Considering Radiation Effects’” (1964, ASME J. Basic Eng., 86, pp. 748–749)

Topics: Design, Radiation (Physics), Reactor vessels

Journal citation

NARROW

Fracture Safety Analysis Concepts for Nuclear Pressure Vessels, Considering the Effects of Irradiation

A Reassessment of Fracture-Safe Operating Criteria for Reactor Vessel Steels Based on Charpy-V Performance

Use of Fracture Mechanics in Reactor Vessel Surveillance

Yankee Reactor Pressure Vessel Surveillance: Notch Ductility Performance of Vessel Steel and Maximum Service Fluence Determined From Exposure During Cores II, III, and IV

Features and Results of Several Programs of Radiation-Damage Surveillance of Power Reactor Pressure Vessels

Reactor-Vessel Design Considering Radiation Effects

Discussion: “Reactor-Vessel Design Considering Radiation Effects” (Porse, L., 1964, ASME J. Basic Eng., 86, pp. 743–748)

Discussion: “Reactor-Vessel Design Considering Radiation Effects” (Porse, L., 1964, ASME J. Basic Eng., 86, pp. 743–748)

Closure to “Discussions of ‘Reactor-Vessel Design Considering Radiation Effects’” (1964, ASME J. Basic Eng., 86, pp. 748–749)

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