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Journal Articles

Ultimate Strength of Thin Wall Tee for Sodium Cooled Fast Reactors Under Seismic Load

Tomoyoshi Watakabe, Hideki Takahashi

J. Pressure Vessel Technol.

Paper No: PVT-23-1034

DOI: https://doi.org/10.1115/1.4062675

Published Online: June 5, 2023

View Article titled, Ultimate Strength of Thin Wall Tee for Sodium Cooled Fast Reactors Under Seismic Load

Topics: Fast neutron reactors, Sodium, Stress, Tensile strength, Thin wall structures, Design, Fatigue, Safety, Dynamic response, Earthquakes

Journal Articles

Development of In-Service Inspection Rules for Liquid-Metal Cooled Reactors Using the System Based Code Concept

Shigeru Takaya, Tai Asayama, Hiroki Yada, A. Thomas Roberts, Frank J. Schaaf, Jr.

J. Pressure Vessel Technol. April 2020, 142(2): 021204.

Paper No: PVT-19-1071

DOI: https://doi.org/10.1115/1.4044344

Published Online: November 27, 2019

View Article titled, Development of In-Service Inspection Rules for Liquid-Metal Cooled Reactors Using the System Based Code Concept

Topics: In-service inspection, Liquid metals, Sodium, Pipes, Heat, Breeder reactors, Fracture (Materials), Welded joints, Reliability, Engineering prototypes

Journal Articles

Design and Integrity Evaluation of a Finned-Tube Sodium-to-Air Heat Exchanger in a Sodium Test Facility

Hyeong-Yeon Lee, Hyungmo Kim, Jong-Bum Kim, Ji-Young Jeong

J. Pressure Vessel Technol. June 2017, 139(3): 031203.

Paper No: PVT-16-1097

DOI: https://doi.org/10.1115/1.4035038

Published Online: November 4, 2016

View Article titled, Design and Integrity Evaluation of a Finned-Tube Sodium-to-Air Heat Exchanger in a Sodium Test Facility

Topics: Design, Sodium, Creep, Stress, Heat exchangers, Fatigue, Test facilities

Journal Articles

Ultimate Strength of a Thin Wall Elbow for Sodium Cooled Fast Reactors Under Seismic Loads

Tomoyoshi Watakabe, Kazuyuki Tsukimori, Seiji Kitamura, Masaki Morishita

J. Pressure Vessel Technol. April 2016, 138(2): 021801.

Paper No: PVT-15-1054

DOI: https://doi.org/10.1115/1.4031721

Published Online: November 19, 2015

View Article titled, Ultimate Strength of a Thin Wall Elbow for Sodium Cooled Fast Reactors Under Seismic Loads

Topics: Design, Failure, Failure mechanisms, Fatigue, Pipes, Stress, Tensile strength, Thin wall structures, Fast neutron reactors, Sodium

Journal Articles

Effect of Temperature and Chloride Content on the Stress Corrosion Cracking Susceptibility of 304 Stainless Steel Welded Joints Treated by Ultrasonic Impact Treatment

Gang Ma, Xiang Ling

J. Pressure Vessel Technol. October 2013, 135(5): 051501.

Paper No: PVT-11-1014

DOI: https://doi.org/10.1115/1.4005871

Published Online: August 26, 2013

View Article titled, Effect of Temperature and Chloride Content on the Stress Corrosion Cracking Susceptibility of 304 Stainless Steel Welded Joints Treated by Ultrasonic Impact Treatment

Topics: Corrosion, Stainless steel, Stress corrosion cracking, Surface roughness, Temperature, Testing, Welded joints, Stress, Sodium

Journal Articles

High Temperature Design and Damage Evaluation of MOD.9Cr-1Mo Steel Heat Exchanger

Hyeong-Yeon Lee, Jong-Bum Kim, Hong-Yune Park

J. Pressure Vessel Technol. October 2012, 134(5): 051101.

DOI: https://doi.org/10.1115/1.4005938

Published Online: September 10, 2012

View Article titled, High Temperature Design and Damage Evaluation of MOD.9Cr-1Mo Steel Heat Exchanger

Topics: Creep, Damage, Design, Fatigue, Finite element analysis, Heat exchangers, High temperature, Sodium, Steel, Stress

Journal Articles

Leak Before Break Analysis of Steam Generator Shell Nozzle Junction for Sodium Cooled Fast Breeder Reactor

N. Mani, G. Thanigaiyarasu, P. Chellapandi

J. Pressure Vessel Technol. April 2012, 134(2): 021211.

DOI: https://doi.org/10.1115/1.4005385

Published Online: January 25, 2012

View Article titled, Leak Before Break Analysis of Steam Generator Shell Nozzle Junction for Sodium Cooled Fast Breeder Reactor

Topics: Boilers, Finite element methods, Fracture (Materials), Junctions, Leakage, Leak-before-break, Nozzles, Shells, Sodium, Sodium fast reactors

Journal Articles

Evaluation Procedures for Irradiation Effects and Sodium Environmental Effects for the Structural Design of Japanese Fast Breeder Reactors

Tai Asayama, Yasuhiro Abe, Noriko Miyaji, Mamoru Koi, Tomohiro Furukawa, Eiichi Yoshida

J. Pressure Vessel Technol. February 2001, 123(1): 49–57.

DOI: https://doi.org/10.1115/1.1338119

Published Online: October 27, 2000

View Article titled, Evaluation Procedures for Irradiation Effects and Sodium Environmental Effects for the Structural Design of Japanese Fast Breeder Reactors

Topics: Corrosion, Creep, Design, Irradiation (Radiation exposure), Mechanical properties, Neutrons, Sodium, Steel, Fluence (Radiation measurement), Breeder reactors

Journal Articles

Numerical Analysis of Nonstationary Thermal Response Characteristics for a Fluid-Structure Interaction System

T. Muramatsu

J. Pressure Vessel Technol. August 1999, 121(3): 276–282.

DOI: https://doi.org/10.1115/1.2883703

Published Online: August 1, 1999

View Article titled, Numerical Analysis of Nonstationary Thermal Response Characteristics for a Fluid-Structure Interaction System

Topics: Fluid structure interaction, Numerical analysis, Fluctuations (Physics), Sodium, Temperature, Damping, Liquid metal fast breeder reactors, Simulation, Turbulence, Boundary element methods

Journal Articles

Seismic Vibration Analysis of Fluid-Structure Interaction in LMFBR Piping Systems

F. Hara

J. Pressure Vessel Technol. May 1988, 110(2): 177–181.

DOI: https://doi.org/10.1115/1.3265583

Published Online: May 1, 1988

View Article titled, Seismic Vibration Analysis of Fluid-Structure Interaction in LMFBR Piping Systems

Topics: Fluid structure interaction, Liquid metal fast breeder reactors, Piping systems, Vibration analysis, Pipes, Pressure, Vibration, Waves, Excitation, Sodium

Journal Articles

The Plastic Ratcheting of Thin Cylindrical Shells Subjected to Axisymmetric Thermal and Mechanical Loading

S. Karadeniz, A. R. S. Ponter, K. F. Carter

J. Pressure Vessel Technol. November 1987, 109(4): 387–393.

DOI: https://doi.org/10.1115/1.3264921

Published Online: November 1, 1987

View Article titled, The Plastic Ratcheting of Thin Cylindrical Shells Subjected to Axisymmetric Thermal and Mechanical Loading

Topics: Pipes, Design, Fast neutron reactors, Finite element analysis, Materials properties, Sodium, Stress, Temperature

Journal Articles

The PVRC International Benchmark Project on Simplified Methods for Elevated Temperature Design and Analysis—An Update

D. H. Pai

J. Pressure Vessel Technol. February 1983, 105(1): 85–90.

DOI: https://doi.org/10.1115/1.3264246

Published Online: February 1, 1983

View Article titled, The PVRC International Benchmark Project on Simplified Methods for Elevated Temperature Design and Analysis—An Update

Topics: Design, Temperature, High temperature, Inelastic analysis, Pressure vessels, Sodium, Structural analysis, Structural mechanics

Journal Articles

TRANS2A: An Unconditionally Stable Code for Thermal Transient Stress Analysis in Piping

B. R. Strong, Jr., G. C. Slagis

J. Pressure Vessel Technol. February 1981, 103(1): 50–58.

DOI: https://doi.org/10.1115/1.3263370

Published Online: February 1, 1981

View Article titled, TRANS2A: An Unconditionally Stable Code for Thermal Transient Stress Analysis in Piping

Topics: Pipes, Stress analysis (Engineering), Transients (Dynamics), Stress, Thermal stresses, Heat transfer, Temperature, Temperature gradient, Unsteady flow, Approximation

Journal Articles

Pressure Transient Analysis of Elbow-Pipe Experiments Using the PTA-2 Computer Code

C. K. Youngdahl, C. A. Kot, R. A. Valentin

J. Pressure Vessel Technol. February 1981, 103(1): 33–42.

DOI: https://doi.org/10.1115/1.3263368

Published Online: February 1, 1981

View Article titled, Pressure Transient Analysis of Elbow-Pipe Experiments Using the PTA-2 Computer Code

Topics: Computers, Pipes, Pressure, Transient analysis, Cavitation, Boilers, Breeder reactors, Computation, Deformation, Heat

Journal Articles

Pressure Transient Analysis in Piping Systems Including the Effects of Plastic Deformation and Cavitation

C. K. Youngdahl, C. A. Kot, R. A. Valentin

J. Pressure Vessel Technol. February 1980, 102(1): 49–55.

DOI: https://doi.org/10.1115/1.3263301

Published Online: February 1, 1980

View Article titled, Pressure Transient Analysis in Piping Systems Including the Effects of Plastic Deformation and Cavitation

Topics: Cavitation, Deformation, Piping systems, Pressure, Transient analysis, Pipes, Sodium, Transients (Dynamics), Waves, Boilers

Journal Articles

Mechanical Properties of Roll Extruded Nuclear Reactor Piping

J. M. Steichen, R. L. Knecht

J. Pressure Vessel Technol. May 1976, 98(2): 105–110.

DOI: https://doi.org/10.1115/1.3454346

Published Online: May 1, 1976

View Article titled, Mechanical Properties of Roll Extruded Nuclear Reactor Piping

Topics: Mechanical properties, Nuclear reactors, Pipes, Temperature, Ductility, Sodium, Tensile strength, ASME Standards, Coolants, Crack propagation

Journal citation

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Manuscript

Ultimate Strength of Thin Wall Tee for Sodium Cooled Fast Reactors Under Seismic Load

Development of In-Service Inspection Rules for Liquid-Metal Cooled Reactors Using the System Based Code Concept

Design and Integrity Evaluation of a Finned-Tube Sodium-to-Air Heat Exchanger in a Sodium Test Facility

Ultimate Strength of a Thin Wall Elbow for Sodium Cooled Fast Reactors Under Seismic Loads

Effect of Temperature and Chloride Content on the Stress Corrosion Cracking Susceptibility of 304 Stainless Steel Welded Joints Treated by Ultrasonic Impact Treatment

High Temperature Design and Damage Evaluation of MOD.9Cr-1Mo Steel Heat Exchanger

Leak Before Break Analysis of Steam Generator Shell Nozzle Junction for Sodium Cooled Fast Breeder Reactor

Evaluation Procedures for Irradiation Effects and Sodium Environmental Effects for the Structural Design of Japanese Fast Breeder Reactors

Numerical Analysis of Nonstationary Thermal Response Characteristics for a Fluid-Structure Interaction System

Seismic Vibration Analysis of Fluid-Structure Interaction in LMFBR Piping Systems

The Plastic Ratcheting of Thin Cylindrical Shells Subjected to Axisymmetric Thermal and Mechanical Loading

The PVRC International Benchmark Project on Simplified Methods for Elevated Temperature Design and Analysis—An Update

TRANS2A: An Unconditionally Stable Code for Thermal Transient Stress Analysis in Piping

Pressure Transient Analysis of Elbow-Pipe Experiments Using the PTA-2 Computer Code

Pressure Transient Analysis in Piping Systems Including the Effects of Plastic Deformation and Cavitation

Mechanical Properties of Roll Extruded Nuclear Reactor Piping

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