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Journal Articles

Thermal Striping Limits Analysis on the Cylinder With a Defect of Liquid-Cooled Nuclear Fast Reactors

Mingda Yu, Juan Du, Xuejiao Shao, Zhuo Pu

Publisher: ASME

J. Pressure Vessel Technol. December 2024, 146(6): 061505.

Paper No: PVT-24-1074

https://doi.org/10.1115/1.4066677

Published Online: October 23, 2024

View Article titled, Thermal Striping Limits Analysis on the Cylinder With a Defect of Liquid-Cooled Nuclear Fast Reactors

Topics: Creep, Cylinders, Damage, Fast neutron reactors, Fatigue, Fracture (Materials), Stress, Temperature, Transients (Dynamics), Stainless steel

Journal Articles

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

Tomoyoshi Watakabe, Hideki Takahashi

Publisher: ASME

J. Pressure Vessel Technol. October 2023, 145(5): 051502.

Paper No: PVT-23-1034

https://doi.org/10.1115/1.4062675

Published Online: June 16, 2023

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

Topics: Design, Failure, Failure mechanisms, Fatigue, Pipes, Stress, Thin wall structures, Dynamic response, Tensile strength, Finite element analysis

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

Publisher: ASME

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

Paper No: PVT-15-1054

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

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 Article titled, 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

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

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

Publisher: ASME

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

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 Accumulation of Damage in Plates Subjected to Steady Mechanical Load and Cyclic Thermal Downshocks on One Surface

J. Phillips

Publisher: ASME

J. Pressure Vessel Technol. August 1982, 104(3): 232–238.

https://doi.org/10.1115/1.3264210

Published Online: August 1, 1982

View Article titled, The Accumulation of Damage in Plates Subjected to Steady Mechanical Load and Cyclic Thermal Downshocks on One Surface

Topics: Damage, Plates (structures), Stress, Creep, Computation, Computers, Design, Fast neutron reactors, Fatigue damage, Hardening

Journal Articles

The Accumulation of Damage in Plates Subjected to Steady Mechanical Load and Cyclic Thermal Downshocks on Both Surfaces

J. Phillips

Publisher: ASME

J. Pressure Vessel Technol. August 1982, 104(3): 239–244.

https://doi.org/10.1115/1.3264211

Published Online: August 1, 1982

View Article titled, The Accumulation of Damage in Plates Subjected to Steady Mechanical Load and Cyclic Thermal Downshocks on Both Surfaces

Topics: Damage, Plates (structures), Stress, Computation, Design, Fast neutron reactors, Materials properties, Transients (Dynamics), Work hardening

Journal citation

NARROW

Thermal Striping Limits Analysis on the Cylinder With a Defect of Liquid-Cooled Nuclear Fast Reactors

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

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

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

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

The Accumulation of Damage in Plates Subjected to Steady Mechanical Load and Cyclic Thermal Downshocks on One Surface

The Accumulation of Damage in Plates Subjected to Steady Mechanical Load and Cyclic Thermal Downshocks on Both Surfaces

ASME Journals

ASME Conference Proceedings

ASME eBooks

Resources

Opportunities

Thermal Striping Limits Analysis on the Cylinder With a Defect of Liquid-Cooled Nuclear Fast Reactors

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

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

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

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

The Accumulation of Damage in Plates Subjected to Steady Mechanical Load and Cyclic Thermal Downshocks on One Surface

The Accumulation of Damage in Plates Subjected to Steady Mechanical Load and Cyclic Thermal Downshocks on Both Surfaces

ASME Journals

ASME Conference Proceedings

ASME eBooks

Resources

Opportunities

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