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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.

Publisher: ASME

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

Paper No: PVT-19-1071

https://doi.org/10.1115/1.4044344

Published Online: November 27, 2019

View Articletitled, 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

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

N. Mani, G. Thanigaiyarasu, P. Chellapandi

Publisher: ASME

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

https://doi.org/10.1115/1.4005385

Published Online: January 25, 2012

View Articletitled, 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

Publisher: ASME

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

https://doi.org/10.1115/1.1338119

Published Online: October 27, 2000

View Articletitled, 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

Analytical Model for Self-Excited Vibration of an Overflow Flexible Plate Weir

S. Kaneko, H. Nagakura, R. Nakano

Publisher: ASME

J. Pressure Vessel Technol. August 1999, 121(3): 296–303.

https://doi.org/10.1115/1.2883706

Published Online: August 1, 1999

View Articletitled, Analytical Model for Self-Excited Vibration of an Overflow Flexible Plate Weir

Topics: Vibration, Sloshing, Stability, Breeder reactors, Collisions (Physics), Eigenfunctions, Momentum, Pressure

Journal Articles

Further Evaluation of Creep-Fatigue Life Prediction Methods for Low-Carbon Nitrogen-Added 316 Stainless Steel

Y. Takahashi

Publisher: ASME

J. Pressure Vessel Technol. May 1999, 121(2): 142–148.

https://doi.org/10.1115/1.2883677

Published Online: May 1, 1999

View Articletitled, Further Evaluation of Creep-Fatigue Life Prediction Methods for Low-Carbon Nitrogen-Added 316 Stainless Steel

Topics: Carbon, Creep, Fatigue, Nitrogen, Stainless steel, Ductility, Breeder reactors, Damage, Failure, Relaxation (Physics)

Journal Articles

Modeling of Multiaxial Creep Behavior for Incoloy 800 Tubes Under Internal Pressure

V. Koundy, T. Forgeron, F. Le Naour

Publisher: ASME

J. Pressure Vessel Technol. August 1997, 119(3): 313–318.

https://doi.org/10.1115/1.2842310

Published Online: August 1, 1997

View Articletitled, Modeling of Multiaxial Creep Behavior for Incoloy 800 Tubes Under Internal Pressure

Topics: Creep, Modeling, Pressure, Stress, Approximation, Boilers, Breeder reactors, Computer simulation, Cycles, Generators

Journal Articles

Assessment of Life of Inner Vessel for a Pool-Type Fast Breeder Reactor Based on Inelastic and Viscoplastic Deformations

R. S. Alwar, P. Chellapandi, S. B. Bhoje

Publisher: ASME

J. Pressure Vessel Technol. May 1993, 115(2): 185–192.

https://doi.org/10.1115/1.2929514

Published Online: May 1, 1993

View Articletitled, Assessment of Life of Inner Vessel for a Pool-Type Fast Breeder Reactor Based on Inelastic and Viscoplastic Deformations

Topics: Breeder reactors, Deformation, Vessels, Creep, Damage, Fatigue, Inelastic analysis, Computation, Computers, Constitutive equations

Journal Articles

Structural Analysis of an LMFBR Shield Assembly Duct Under Thermo-Mechanical and Seismic Loads

S. N. Malik, V. K. Sazawal

Publisher: ASME

J. Pressure Vessel Technol. May 1986, 108(2): 151–157.

https://doi.org/10.1115/1.3264763

Published Online: May 1, 1986

View Articletitled, Structural Analysis of an LMFBR Shield Assembly Duct Under Thermo-Mechanical and Seismic Loads

Topics: Ducts, Liquid metal fast breeder reactors, Manufacturing, Stress, Structural analysis, Thermomechanics, Stress analysis (Engineering), Creep, Fatigue, Temperature

Journal Articles

Plastic Buckling of Short Vertical Cylindrical Shells Subjected to Horizontal Edge Shear Loads

G. D. Galletly, J. BŁachut

Publisher: ASME

J. Pressure Vessel Technol. May 1985, 107(2): 101–106.

https://doi.org/10.1115/1.3264420

Published Online: May 1, 1985

View Articletitled, Plastic Buckling of Short Vertical Cylindrical Shells Subjected to Horizontal Edge Shear Loads

Topics: Buckling, Pipes, Shear (Mechanics), Stress, Design, Breeder reactors, Die cutting, Liquid metal fast breeder reactors, Nuclear industry, Shearing (Deformation)

Journal Articles

Trial Application of the Draft Structural Design Criteria for Breeder Reactor Core Components to a Typical Blanket Assembly Duct

V. K. Sazawal

Publisher: ASME

J. Pressure Vessel Technol. November 1981, 103(4): 380–387.

https://doi.org/10.1115/1.3263417

Published Online: November 1, 1981

View Articletitled, Trial Application of the Draft Structural Design Criteria for Breeder Reactor Core Components to a Typical Blanket Assembly Duct

Topics: Breeder reactors, Ducts, Manufacturing, Structural design, Design, Failure mechanisms

Journal Articles

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

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

Publisher: ASME

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

https://doi.org/10.1115/1.3263368

Published Online: February 1, 1981

View Articletitled, 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

Publisher: ASME

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

https://doi.org/10.1115/1.3263301

Published Online: February 1, 1980

View Articletitled, 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

Inelastic Behavior of Finite Circular Cylindrical Shells

J. M. Chern, D. H. Pai

Publisher: ASME

J. Pressure Vessel Technol. February 1977, 99(1): 31–38.

https://doi.org/10.1115/1.3454518

Published Online: February 1, 1977

View Articletitled, Inelastic Behavior of Finite Circular Cylindrical Shells

Topics: Circular cylindrical shells, Design, Inelastic analysis, Liquid metal fast breeder reactors, Stress, Approximation, Creep, Temperature, Boundary-value problems, Breeder reactors

Journal Articles

An Evaluation of the Material Capabilities of Low Carbon 2 1/4 Cr-1 Mo Steel Forgings

F. P. Fetterolf, J. H. Hurtt

Publisher: ASME

J. Pressure Vessel Technol. November 1976, 98(4): 316–322.

https://doi.org/10.1115/1.3454417

Published Online: November 1, 1976

View Articletitled, An Evaluation of the Material Capabilities of Low Carbon 2 1/4 Cr-1 Mo Steel Forgings

Topics: Carbon, Forgings (Products), Steel, Breeder reactors, Heat, Mechanical properties, Nuclear power, Operating temperature, Rivers, Steam

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

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

Analytical Model for Self-Excited Vibration of an Overflow Flexible Plate Weir

Further Evaluation of Creep-Fatigue Life Prediction Methods for Low-Carbon Nitrogen-Added 316 Stainless Steel

Modeling of Multiaxial Creep Behavior for Incoloy 800 Tubes Under Internal Pressure

Assessment of Life of Inner Vessel for a Pool-Type Fast Breeder Reactor Based on Inelastic and Viscoplastic Deformations

Structural Analysis of an LMFBR Shield Assembly Duct Under Thermo-Mechanical and Seismic Loads

Plastic Buckling of Short Vertical Cylindrical Shells Subjected to Horizontal Edge Shear Loads

Trial Application of the Draft Structural Design Criteria for Breeder Reactor Core Components to a Typical Blanket Assembly Duct

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

Inelastic Behavior of Finite Circular Cylindrical Shells

An Evaluation of the Material Capabilities of Low Carbon 2 1/4 Cr-1 Mo Steel Forgings

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