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Journal Articles

Investigation of the Beltline Welding Seam and Base Metal of the Greifswald WWER-440 Unit 1 Reactor Pressure Vessel

Jan Schuhknecht, Hans-Werner Viehrig, Udo Rindelhardt

Publisher: ASME

J. Eng. Gas Turbines Power. May 2011, 133(5): 052904.

https://doi.org/10.1115/1.4000891

Published Online: December 9, 2010

View Article titled, Investigation of the Beltline Welding Seam and Base Metal of the Greifswald WWER-440 Unit 1 Reactor Pressure Vessel

Topics: Base metals, Metals, Reactor vessels, Temperature, Welding, Electromagnetic scattering, Fracture (Materials), Fracture toughness, Nuclear power stations, Steel

Journal Articles

Industry Practice for the Neutron Irradiation Embrittlement of Reactor Pressure Vessels in Japan

Norimichi Yamashita, Masanobu Iwasaki, Koji Dozaki, Naoki Soneda

Publisher: ASME

J. Eng. Gas Turbines Power. October 2010, 132(10): 102919.

https://doi.org/10.1115/1.4001057

Published Online: July 9, 2010

View Article titled, Industry Practice for the Neutron Irradiation Embrittlement of Reactor Pressure Vessels in Japan

Topics: Embrittlement, Irradiation (Radiation exposure), Neutrons, Surveillance, Steel, Reactor vessels

Journal Articles

Characteristics of the New Embrittlement Correlation Method for the Japanese Reactor Pressure Vessel Steels

Naoki Soneda, Akiyoshi Nomoto

Publisher: ASME

J. Eng. Gas Turbines Power. October 2010, 132(10): 102918.

https://doi.org/10.1115/1.4001056

Published Online: July 9, 2010

View Article titled, Characteristics of the New Embrittlement Correlation Method for the Japanese Reactor Pressure Vessel Steels

Topics: Embrittlement, Reactor vessels, Steel, Surveillance, Copper, Irradiation (Radiation exposure), Phase transition temperature, Nickel

Journal Articles

Weld Material Investigations of a WWER-440 Reactor Pressure Vessel: Results From the First Trepan Taken From the Former Greifswald NPP

Udo Rindelhardt, Hans-Werner Viehrig, Joerg Konheiser, Jan Schuhknecht

Publisher: ASME

J. Eng. Gas Turbines Power. March 2009, 131(2): 022904.

https://doi.org/10.1115/1.3032461

Published Online: January 5, 2009

View Article titled, Weld Material Investigations of a WWER-440 Reactor Pressure Vessel: Results From the First Trepan Taken From the Former Greifswald NPP

Topics: Annealing, Fluence (Radiation measurement), Neutrons, Nuclear power stations, Temperature, Fracture toughness, Welded joints, Reactor vessels, Disks

Journal Articles

The Nuclear Closed-Cycle Gas Turbine (HTGR-GT)—Dry Cooled Commercial Power Plant Studies

Colin F. McDonald, Charles R. Boland

Publisher: ASME

J. Eng. Gas Turbines Power. January 1981, 103(1): 89–100.

https://doi.org/10.1115/1.3230712

Published Online: January 1, 1981

View Article titled, The Nuclear Closed-Cycle Gas Turbine (HTGR-GT)—Dry Cooled Commercial Power Plant Studies

Topics: Closed-cycle gas turbines, Power stations, Very high temperature reactors, Design, Energy conversion, Cycles, Gas turbines, Power conversion systems, Prestressed concrete, Reactor vessels

Journal Articles

An Efficient, Flexible Arrangement to Generate High Quality Process or Domestic Heat in Recuperative Gas Cycle Power Plants: Application to Helium Direct Cycle Nuclear Power Plants

Z. P. Tilliette, B. Pierre, P. F. Jude

Publisher: ASME

J. Eng. Gas Turbines Power. January 1979, 101(1): 130–140.

https://doi.org/10.1115/1.3446434

Published Online: January 1, 1979

View Article titled, An Efficient, Flexible Arrangement to Generate High Quality Process or Domestic Heat in Recuperative Gas Cycle Power Plants: Application to Helium Direct Cycle Nuclear Power Plants

Topics: Cycles, Heat, Helium, Nuclear power stations, Power stations, Pressure, Boilers, Circuits, Cooling, Electric power generation

Journal Articles

Heat Exchanger Design Considerations for Gas Turbine HTGR Power Plant

C. F. McDonald, T. Van Hagan, K. Vepa

Publisher: ASME

J. Eng. Gas Turbines Power. April 1977, 99(2): 237–245.

https://doi.org/10.1115/1.3446278

Published Online: April 1, 1977

View Article titled, Heat Exchanger Design Considerations for Gas Turbine HTGR Power Plant

Topics: Design, Gas turbines, Heat exchangers, Power stations, Very high temperature reactors, Cycles, Helium, Heat, Fluids, Temperature

Journal Articles

Development of Jet Pumps for Boiling Water Reactor Recirculation Systems

A. A. Kudirka, D. M. Gluntz

Publisher: ASME

J. Eng. Gas Turbines Power. January 1974, 96(1): 7–12.

https://doi.org/10.1115/1.3445755

Published Online: January 1, 1974

View Article titled, Development of Jet Pumps for Boiling Water Reactor Recirculation Systems

Topics: Boiling water reactors, Jet pumps, Geometry, Reactor vessels, Subcooling, Water

Journal Articles

The Effect of Nozzle Spacing on the Pressure Stresses at the Intersection of Cylindrical Nozzles and Shells

R. M. Stone, S. Hochschild

Publisher: ASME

J. Eng. Gas Turbines Power. July 1967, 89(3): 360–368.

https://doi.org/10.1115/1.3616694

Published Online: July 1, 1967

View Article titled, The Effect of Nozzle Spacing on the Pressure Stresses at the Intersection of Cylindrical Nozzles and Shells

Topics: Nozzles, Pressure, Shells, Stress, ASME Boiler and Pressure Vessel Code, Pressure vessels, Reactor vessels

Journal Articles

Some Notes on the Strength of the Enrico Fermi Reactor Vessel Structure

F. R. Beyer

Publisher: ASME

J. Eng. Gas Turbines Power. January 1959, 81(1): 66–72.

https://doi.org/10.1115/1.4008010

Published Online: January 1, 1959

View Article titled, Some Notes on the Strength of the Enrico Fermi Reactor Vessel Structure

Topics: Reactor vessels, Design, Gages, High temperature, Hydrostatic testing, Nuclear power stations, Nuclear structure, Strain gages

Journal citation

NARROW

Investigation of the Beltline Welding Seam and Base Metal of the Greifswald WWER-440 Unit 1 Reactor Pressure Vessel

Industry Practice for the Neutron Irradiation Embrittlement of Reactor Pressure Vessels in Japan

Characteristics of the New Embrittlement Correlation Method for the Japanese Reactor Pressure Vessel Steels

Weld Material Investigations of a WWER-440 Reactor Pressure Vessel: Results From the First Trepan Taken From the Former Greifswald NPP

The Nuclear Closed-Cycle Gas Turbine (HTGR-GT)—Dry Cooled Commercial Power Plant Studies

An Efficient, Flexible Arrangement to Generate High Quality Process or Domestic Heat in Recuperative Gas Cycle Power Plants: Application to Helium Direct Cycle Nuclear Power Plants

Heat Exchanger Design Considerations for Gas Turbine HTGR Power Plant

Development of Jet Pumps for Boiling Water Reactor Recirculation Systems

The Effect of Nozzle Spacing on the Pressure Stresses at the Intersection of Cylindrical Nozzles and Shells

Some Notes on the Strength of the Enrico Fermi Reactor Vessel Structure

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