1-20 of 70
Fast neutron reactors
Close
Save search
Follow your search
Access your saved searches in your account
Would you like to receive an alert when new items match your search?
Close Modal
Sort by
Proceedings Papers

Development of the Buckling Evaluation Method for Large Scale Vessels in Fast Reactors Made of Grade 91 Steel and Austenitic Stainless Steel With Large Initial Imperfections

Takashi Okafuji, Kazuhiro Miura, Hiromi Sago, Hisatomo Murakami, Tomoyoshi Watakabe, Masanori Ando, Masashi Miyazaki
Proc. ASME. PVP2024, Volume 1: Codes & Standards; Computer Technology & Bolted Joints, V001T01A035, July 28–August 2, 2024
Publisher: American Society of Mechanical Engineers
Paper No: PVP2024-123103
https://doi.org/10.1115/PVP2024-123103
View Paper titled, Development of the Buckling Evaluation Method for Large Scale Vessels in Fast Reactors Made of Grade 91 Steel and Austenitic Stainless Steel With Large Initial Imperfections
Open the PDF for Development of the Buckling Evaluation Method for Large Scale Vessels in Fast Reactors Made of Grade 91 Steel and Austenitic Stainless Steel With Large Initial Imperfections in another window
Topics: Buckling, Evaluation methods, Fast neutron reactors, Stainless steel, Steel, Vessels, Stress, Design, Power stations, Wall thickness
Proceedings Papers

Development of the Buckling Evaluation Method for Large Scale Vessels in Fast Reactors by the Testing of Grade 91 Steel and Austenitic Stainless Steel Vessels Subjected to Horizontal and Cyclic Vertical Loading

Takashi Okafuji, Kazuhiro Miura, Hiromi Sago, Hisatomo Murakami, Masanori Ando, Satoshi Okajima
Proc. ASME. PVP2023, Volume 1: Codes & Standards, V001T01A037, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-105707
https://doi.org/10.1115/PVP2023-105707
View Paper titled, Development of the Buckling Evaluation Method for Large Scale Vessels in Fast Reactors by the Testing of Grade 91 Steel and Austenitic Stainless Steel Vessels Subjected to Horizontal and Cyclic Vertical Loading
Open the PDF for Development of the Buckling Evaluation Method for Large Scale Vessels in Fast Reactors by the Testing of Grade 91 Steel and Austenitic Stainless Steel Vessels Subjected to Horizontal and Cyclic Vertical Loading in another window
Topics: Buckling, Evaluation methods, Fast neutron reactors, Stainless steel, Steel, Testing, Vessels, Stress, Design, Yield stress
Proceedings Papers

Study on Dynamic Buckling Behavior and Post-Buckling Stability of Thin-Walled Cylinders Subjected to Lateral Vibration

Yiji Ye, Sho Hasegawa, Naoto Kasahara
Proc. ASME. PVP2023, Volume 7: Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division, V007T08A008, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-105543
https://doi.org/10.1115/PVP2023-105543
View Paper titled, Study on Dynamic Buckling Behavior and Post-Buckling Stability of Thin-Walled Cylinders Subjected to Lateral Vibration
Open the PDF for Study on Dynamic Buckling Behavior and Post-Buckling Stability of Thin-Walled Cylinders Subjected to Lateral Vibration in another window
Topics: Buckling, Cylinders, Design, Earthquakes, Fast neutron reactors, Stability, Vessels, Vibration
Proceedings Papers

Development of the Buckling Evaluation Method for Large Scale Vessel in Fast Reactors by the Testing of Austenitic Stainless Steel Vessel With Severe Initial Imperfection Subjected to Horizontal and Vertical Loading

Takashi Okafuji, Kazuhiro Miura, Hiromi Sago, Hisatomo Murakami, Masanori Ando, Satoshi Okajima
Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A032, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-84605
https://doi.org/10.1115/PVP2022-84605
View Paper titled, Development of the Buckling Evaluation Method for Large Scale Vessel in Fast Reactors by the Testing of Austenitic Stainless Steel Vessel With Severe Initial Imperfection Subjected to Horizontal and Vertical Loading
Open the PDF for Development of the Buckling Evaluation Method for Large Scale Vessel in Fast Reactors by the Testing of Austenitic Stainless Steel Vessel With Severe Initial Imperfection Subjected to Horizontal and Vertical Loading in another window
Topics: Buckling, Evaluation methods, Fast neutron reactors, Stainless steel, Testing, Vessels, Steel, Stress, Design, Power stations
Proceedings Papers

Development of the Buckling Evaluation Method for Large Scale Vessel by the Testing of Gr. 91 Vessel Subjected to Horizontal and Cyclic Vertical Loading

Takashi Okafuji, Kazuhiro Miura, Hiromi Sago, Hisatomo Murakami, Masanori Ando, Masashi Miyazaki
Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A016, July 13–15, 2021
Publisher: American Society of Mechanical Engineers
Paper No: PVP2021-60672
https://doi.org/10.1115/PVP2021-60672
View Paper titled, Development of the Buckling Evaluation Method for Large Scale Vessel by the Testing of Gr. 91 Vessel Subjected to Horizontal and Cyclic Vertical Loading
Open the PDF for Development of the Buckling Evaluation Method for Large Scale Vessel by the Testing of Gr. 91 Vessel Subjected to Horizontal and Cyclic Vertical Loading in another window
Topics: Buckling, Evaluation methods, Testing, Vessels, Stress, Shapes, Design, Fast neutron reactors, Plates (structures), Power stations
Proceedings Papers

Development of Leak Before Break Assessment Guidelines for Sodium Cooled Fast Reactors in Japan

Hiroki Yada, Takashi Wakai, Takayuki Miyagawa, Hideo Machida
Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A060, July 13–15, 2021
Publisher: American Society of Mechanical Engineers
Paper No: PVP2021-61942
https://doi.org/10.1115/PVP2021-61942
View Paper titled, Development of Leak Before Break Assessment Guidelines for Sodium Cooled Fast Reactors in Japan
Open the PDF for Development of Leak Before Break Assessment Guidelines for Sodium Cooled Fast Reactors in Japan in another window
Topics: Fast neutron reactors, Fracture (Materials), In-service inspection, Leakage, Leak-before-break, Sodium, Sodium fast reactors
Proceedings Papers

Experimental Study on the Effect of Core Support Frame on Seismic Behavior of Fast Reactor Core

Shinichiro Matsubara, Akihisa Iwasaki, Hidenori Harada, Tomohiko Yamamoto
Proc. ASME. PVP2020, Volume 9: Seismic Engineering, V009T09A023, August 3, 2020
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21385
https://doi.org/10.1115/PVP2020-21385
View Paper titled, Experimental Study on the Effect of Core Support Frame on Seismic Behavior of Fast Reactor Core
Open the PDF for Experimental Study on the Effect of Core Support Frame on Seismic Behavior of Fast Reactor Core in another window
Topics: Fast neutron reactors, Earthquakes, Vibration, Collisions (Physics), Compacting, Displacement, Elongation, Fluid structure interaction, Vibration analysis
Proceedings Papers

Analysis of Seismic Experiment of Hexagonal Multi Bundle Model Using Core Assembly Mock-Up

Akihisa Iwasaki, Shinichiro Matsubara, Hidenori Harada, Tomohiko Yamamoto
Proc. ASME. PVP2020, Volume 9: Seismic Engineering, V009T09A024, August 3, 2020
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21386
https://doi.org/10.1115/PVP2020-21386
View Paper titled, Analysis of Seismic Experiment of Hexagonal Multi Bundle Model Using Core Assembly Mock-Up
Open the PDF for Analysis of Seismic Experiment of Hexagonal Multi Bundle Model Using Core Assembly Mock-Up in another window
Topics: Manufacturing, Fast neutron reactors, Vibration, Displacement, Earthquakes, Boundary-value problems, Collisions (Physics), Elongation, Fluid structure interaction, Vibration analysis
Proceedings Papers

Development of the Buckling Evaluation Method for Large Scale Vessel by the Testing of Gr. 91 Vessel Subjected to Vertical and Horizontal Loading

Takashi Okafuji, Kazuhiro Miura, Hiromi Sago, Hisatomo Murakami, Masanori Ando, Masashi Miyazaki
Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A047, August 3, 2020
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21328
https://doi.org/10.1115/PVP2020-21328
View Paper titled, Development of the Buckling Evaluation Method for Large Scale Vessel by the Testing of Gr. 91 Vessel Subjected to Vertical and Horizontal Loading
Open the PDF for Development of the Buckling Evaluation Method for Large Scale Vessel by the Testing of Gr. 91 Vessel Subjected to Vertical and Horizontal Loading in another window
Topics: Buckling, Evaluation methods, Testing, Vessels, Stress, Compression, Shear (Mechanics), Steel, Design, Japan Society of Mechanical Engineers
Proceedings Papers

Effect of Deformation of Core Elements of Fast Reactor Core to the Seismic Response

Akihisa Iwasaki, Shinichiro Matsubara, Kazuteru Kawamura, Hidenori Harada, Tomohiko Yamamoto
Proc. ASME. PVP2019, Volume 8: Seismic Engineering, V008T08A040, July 14–19, 2019
Publisher: American Society of Mechanical Engineers
Paper No: PVP2019-93769
https://doi.org/10.1115/PVP2019-93769
View Paper titled, Effect of Deformation of Core Elements of Fast Reactor Core to the Seismic Response
Open the PDF for Effect of Deformation of Core Elements of Fast Reactor Core to the Seismic Response in another window
Topics: Deformation, Fast neutron reactors, Displacement, Earthquakes, Seismic analysis, Thermal expansion, Collisions (Physics), Fluid structure interaction, Nozzles, Vibration
Proceedings Papers

Fast Reactor Core Seismic Analysis for Verification of Assessment Model Considering Deformation of Core Elements

Shinichiro Matsubara, Akihisa Iwasaki, Kazuteru Kawamura, Hidenori Harada, Tomohiko Yamamoto
Proc. ASME. PVP2019, Volume 8: Seismic Engineering, V008T08A041, July 14–19, 2019
Publisher: American Society of Mechanical Engineers
Paper No: PVP2019-93778
https://doi.org/10.1115/PVP2019-93778
View Paper titled, Fast Reactor Core Seismic Analysis for Verification of Assessment Model Considering Deformation of Core Elements
Open the PDF for Fast Reactor Core Seismic Analysis for Verification of Assessment Model Considering Deformation of Core Elements in another window
Topics: Deformation, Fast neutron reactors, Seismic analysis, Vibration, Vibration tests, Displacement, Fluid structure interaction, Fluids, Irradiation (Radiation exposure), Thermal expansion
Proceedings Papers

Fast Reactor Core Seismic Experiment and Analysis Under Strong Excitation

Tomohiko Yamamoto, Akihisa Iwasaki, Kazuteru Kawamura, Shinichiro Matsubara, Hidenori Harada
Proc. ASME. PVP2018, Volume 8: Seismic Engineering, V008T08A046, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84466
https://doi.org/10.1115/PVP2018-84466
View Paper titled, Fast Reactor Core Seismic Experiment and Analysis Under Strong Excitation
Open the PDF for Fast Reactor Core Seismic Experiment and Analysis Under Strong Excitation in another window
Topics: Excitation, Fast neutron reactors, Design, Dimensions, Displacement, Fluid structure interaction, Seismic analysis, Shapes, Vibration, Vibration analysis
Proceedings Papers

Fast Reactor Core Seismic Experiment of Full Scale Single Model of Control Rod

Akihisa Iwasaki, Shinichiro Matsubara, Kazuteru Kawamura, Hidenori Harada, Tomohiko Yamamoto
Proc. ASME. PVP2018, Volume 8: Seismic Engineering, V008T08A047, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84471
https://doi.org/10.1115/PVP2018-84471
View Paper titled, Fast Reactor Core Seismic Experiment of Full Scale Single Model of Control Rod
Open the PDF for Fast Reactor Core Seismic Experiment of Full Scale Single Model of Control Rod in another window
Topics: Coolants, Displacement, Earthquakes, Excitation, Fast neutron reactors, Friction, Fuels, Manufacturing, Pressure, Shock absorbers
Proceedings Papers

Fast Reactor Cores: Seismic Excitation in the Vertical Direction — Numerical Methods

Daniel Broc, Gianluca Artini, Jérome Cardolaccia, Laurent Martin
Proc. ASME. PVP2018, Volume 8: Seismic Engineering, V008T08A042, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84098
https://doi.org/10.1115/PVP2018-84098
View Paper titled, Fast Reactor Cores: Seismic Excitation in the Vertical Direction — Numerical Methods
Open the PDF for Fast Reactor Cores: Seismic Excitation in the Vertical Direction — Numerical Methods in another window
Topics: Excitation, Fast neutron reactors, Numerical analysis, Fluids, Fuels, Sodium, Boundary-value problems, Computers, Coolants, Design
Proceedings Papers

Fast Reactor Core Seismic Analysis for Verification of Assessment Model of Control Rod

Akihisa Iwasaki, Shinichiro Matsubara, Kazuteru Kawamura, Hidenori Harada, Tomohiko Yamamoto
Proc. ASME. PVP2018, Volume 8: Seismic Engineering, V008T08A048, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84474
https://doi.org/10.1115/PVP2018-84474
View Paper titled, Fast Reactor Core Seismic Analysis for Verification of Assessment Model of Control Rod
Open the PDF for Fast Reactor Core Seismic Analysis for Verification of Assessment Model of Control Rod in another window
Topics: Displacement, Earthquakes, Fast neutron reactors, Fuels, Manufacturing, Pressure, Seismic analysis, Shock absorbers
Proceedings Papers

Failure Mode of ED and AD Type Head Plates Subject to Convex Side Pressure

Hiroki Yada, Masanori Ando, Kazuyuki Tsukimori, Masakazu Ichimiya, Yoshinari Anoda
Proc. ASME. PVP2017, Volume 3B: Design and Analysis, V03BT03A002, July 16–20, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVP2017-65227
https://doi.org/10.1115/PVP2017-65227
View Paper titled, Failure Mode of ED and AD Type Head Plates Subject to Convex Side Pressure
Open the PDF for Failure Mode of ED and AD Type Head Plates Subject to Convex Side Pressure in another window
Topics: Failure mechanisms, Plates (structures), Pressure, Fracture (Materials), Containment vessels, Failure, Deformation, Design, Fracture toughness, Leakage
Proceedings Papers

Fluid Structure Interaction for Tubes Bundles: Different Homogenization Methods

Daniel Broc, Gianluca Artini
Proc. ASME. PVP2017, Volume 4: Fluid-Structure Interaction, V004T04A052, July 16–20, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVP2017-65727
https://doi.org/10.1115/PVP2017-65727
View Paper titled, Fluid Structure Interaction for Tubes Bundles: Different Homogenization Methods
Open the PDF for Fluid Structure Interaction for Tubes Bundles: Different Homogenization Methods in another window
Topics: Fluid structure interaction, Fluids, Fluid dynamics, Damping, Excitation, Fast neutron reactors, Sodium, Theoretical analysis, Boilers, Computer simulation
Proceedings Papers

Numerical Analysis of Flow-Induced Vibration of Large Diameter Pipe With Short Elbow

Shigeru Takaya, Tatsuya Fujisaki, Masaaki Tanaka
Proc. ASME. PVP2017, Volume 4: Fluid-Structure Interaction, V004T04A006, July 16–20, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVP2017-65601
https://doi.org/10.1115/PVP2017-65601
View Paper titled, Numerical Analysis of Flow-Induced Vibration of Large Diameter Pipe With Short Elbow
Open the PDF for Numerical Analysis of Flow-Induced Vibration of Large Diameter Pipe With Short Elbow in another window
Topics: Flow-induced vibrations, Numerical analysis, Pipes, Pressure, Design, Stress, Computer simulation, Flow (Dynamics), Construction, Cooling systems
Proceedings Papers

Core Seismic Experiment and Analysis of Full Scale Single Model for Fast Reactor

Akihisa Iwasaki, Shinichiro Matsubara, Tomohiko Yamamoto, Seiji Kitamura, Hidenori Harada
Proc. ASME. PVP2017, Volume 8: Seismic Engineering, V008T08A050, July 16–20, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVP2017-65329
https://doi.org/10.1115/PVP2017-65329
View Paper titled, Core Seismic Experiment and Analysis of Full Scale Single Model for Fast Reactor
Open the PDF for Core Seismic Experiment and Analysis of Full Scale Single Model for Fast Reactor in another window
Topics: Fast neutron reactors, Displacement, Design, Dimensions, Earthquakes, Fluid structure interaction, Seismic analysis, Vibration analysis
Proceedings Papers

Fluid Structure Interaction for Tubes Bundles: Presentation of a Linear Equivalent Model

Daniel Broc, Gianluca Artini
Proc. ASME. PVP2017, Volume 4: Fluid-Structure Interaction, V004T04A051, July 16–20, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVP2017-65725
https://doi.org/10.1115/PVP2017-65725
View Paper titled, Fluid Structure Interaction for Tubes Bundles: Presentation of a Linear Equivalent Model
Open the PDF for Fluid Structure Interaction for Tubes Bundles: Presentation of a Linear Equivalent Model in another window
Topics: Boilers, Computer simulation, Coolants, Damping, Earthquakes, Engineering prototypes, Excitation, Fast neutron reactors, Fluid dynamics, Fluid structure interaction