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Journal Articles

Cylindrical IEC Fusion Neutron Source for Broad Area NAA

George H. Miley, Hiromu Momota, Hugo Leon, Ben Ulmen, Guilherme Amadio, Atanu Khan, George Chen, William Matisiak, Ali Azeem, Paul Keutelian

Publisher: ASME

J. Eng. Gas Turbines Power. December 2011, 133(12): 124502.

https://doi.org/10.1115/1.4002889

Published Online: September 14, 2011

View Article titled, Cylindrical IEC Fusion Neutron Source for Broad Area NAA

Topics: Design, Inspection, Neutron activation analysis, Neutron sources, Neutrons, Explosives, Plasmas (Ionized gases), Sensors, X-rays, Geometry

Journal Articles

A Parametric Study of Fuel Lattice Design for HTR-10

Meng-Jen Wang, Jinn-Jer Peir, Chen-Wei Chi, Jenq-Horng Liang

Publisher: ASME

J. Eng. Gas Turbines Power. August 2011, 133(8): 084503.

https://doi.org/10.1115/1.4002879

Published Online: April 11, 2011

View Article titled, A Parametric Study of Fuel Lattice Design for HTR-10

Topics: Fuels, Neutrons, Design

Journal Articles

The Design of an Ambient Neutron Dose-Equivalent Meter

Xia Wenming, Jia Mingchun, Guo Zhirong

Publisher: ASME

J. Eng. Gas Turbines Power. August 2011, 133(8): 084501.

https://doi.org/10.1115/1.4002818

Published Online: April 8, 2011

View Article titled, The Design of an Ambient Neutron Dose-Equivalent Meter

Topics: Design, Dosimeters, Fluence (Radiation measurement), Neutrons, Sensors, Electronics

Journal Articles

Transfer Function Modeling of Zero-Power Dynamics of Circulating Fuel Reactors

A. Cammi, V. Di Marcello, C. Guerrieri, L. Luzzi

Publisher: ASME

J. Eng. Gas Turbines Power. May 2011, 133(5): 052916.

https://doi.org/10.1115/1.4002880

Published Online: December 21, 2010

View Article titled, Transfer Function Modeling of Zero-Power Dynamics of Circulating Fuel Reactors

Topics: Circuits, Coolants, Dynamics (Mechanics), Fuels, Neutrons, Steady state, Transfer functions, Modeling, Nuclear reactors, Density

Journal Articles

CANDU Reactor Space-Time Kinetic Model for Load Following Studies

Lingzhi Xia, Jin Jiang

Publisher: ASME

J. Eng. Gas Turbines Power. May 2011, 133(5): 052915.

https://doi.org/10.1115/1.4002870

Published Online: December 21, 2010

View Article titled, CANDU Reactor Space-Time Kinetic Model for Load Following Studies

Topics: Matlab, Modeling, Neutron flux, Neutrons, Nuclear reactor kinetics, Simulation, Simulation results, Spacetime, Steady state, Stress

Journal Articles

Study on the Coupled Neutronic and Thermal-Hydraulic Characteristics of the New Concept Molten Salt Reactor

Peng Wang, Libo Qian, Dalin Zhang, Wenxi Tian, Guanghui Su, Suizheng Qiu

Publisher: ASME

J. Eng. Gas Turbines Power. October 2010, 132(10): 102923.

https://doi.org/10.1115/1.4001067

Published Online: July 14, 2010

View Article titled, Study on the Coupled Neutronic and Thermal-Hydraulic Characteristics of the New Concept Molten Salt Reactor

Topics: Flow (Dynamics), Flux (Metallurgy), Fuels, Inflow, Molten salt reactors, Neutrons, Steady state, Temperature, Computer programming, Momentum

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

A Once-Through Fuel Cycle for Fast Reactors

Kevan D. Weaver, John Gilleland, Charles Ahlfeld, Charles Whitmer, George Zimmerman

Publisher: ASME

J. Eng. Gas Turbines Power. October 2010, 132(10): 102917.

https://doi.org/10.1115/1.4000898

Published Online: July 8, 2010

View Article titled, A Once-Through Fuel Cycle for Fast Reactors

Topics: Fast neutron reactors, Fuels, Light water reactors, Nuclear fuel cycle, Uranium, Design, Spent nuclear fuels, Waves, Traveling waves, Nuclear power

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

Neutron and Positron Techniques for Fluid Transfer System Analysis and Remote Temperature and Stress Measurement

P. A. E. Stewart

Publisher: ASME

J. Eng. Gas Turbines Power. April 1988, 110(2): 279–288.

https://doi.org/10.1115/1.3240118

Published Online: April 1, 1988

View Article titled, Neutron and Positron Techniques for Fluid Transfer System Analysis and Remote Temperature and Stress Measurement

Topics: Fluids, Neutrons, Positrons, Stress, Systems analysis, Temperature, Engines, Compressors, Disks, Inspection

Journal Articles

LMFBR Operational and Experimental In-Core, Local-Fault Experience, Primarily With Oxide Fuel Elements

D. K. Warinner

Publisher: ASME

J. Eng. Gas Turbines Power. July 1983, 105(3): 669–678.

https://doi.org/10.1115/1.3227468

Published Online: July 1, 1983

View Article titled, LMFBR Operational and Experimental In-Core, Local-Fault Experience, Primarily With Oxide Fuel Elements

Topics: Fuels, Liquid metal fast breeder reactors, Failure, Neutrons, Nuclear fission, Signals, Sodium, Thermal reactors

Journal Articles

The LMFBR Fuel-Design Environment for Endurance Testing, Primarily of Oxide Fuel Elements With Local Faults

D. K. Warinner

Publisher: ASME

J. Eng. Gas Turbines Power. July 1983, 105(3): 679–689.

https://doi.org/10.1115/1.3227469

Published Online: July 1, 1983

View Article titled, The LMFBR Fuel-Design Environment for Endurance Testing, Primarily of Oxide Fuel Elements With Local Faults

Topics: Design, Fuels, Liquid metal fast breeder reactors, Testing, Failure, Neutrons, Nuclear fission

Journal Articles

Special Engineering Problems of TFTR

D. E. Lee

Publisher: ASME

J. Eng. Gas Turbines Power. July 1978, 100(3): 417–423.

https://doi.org/10.1115/1.3446373

Published Online: July 1, 1978

View Article titled, Special Engineering Problems of TFTR

Topics: Boron, Concretes, Damage, Design, Electrical resistivity, Engineering design, Fuels, Machine components, Machinery, Magnetic fields

Journal citation

NARROW

Cylindrical IEC Fusion Neutron Source for Broad Area NAA

A Parametric Study of Fuel Lattice Design for HTR-10

The Design of an Ambient Neutron Dose-Equivalent Meter

Transfer Function Modeling of Zero-Power Dynamics of Circulating Fuel Reactors

CANDU Reactor Space-Time Kinetic Model for Load Following Studies

Study on the Coupled Neutronic and Thermal-Hydraulic Characteristics of the New Concept Molten Salt Reactor

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

A Once-Through Fuel Cycle for Fast Reactors

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

Neutron and Positron Techniques for Fluid Transfer System Analysis and Remote Temperature and Stress Measurement

LMFBR Operational and Experimental In-Core, Local-Fault Experience, Primarily With Oxide Fuel Elements

The LMFBR Fuel-Design Environment for Endurance Testing, Primarily of Oxide Fuel Elements With Local Faults

Special Engineering Problems of TFTR

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