Search Results | PVP | ASME Digital Collection

1-20 of 64

2 3 4

Sort by

Sort Order Select

Proceedings Papers

Seismic Assessment of Crossover Piping on a Sodium Cooled Fast Reactor With Three-Dimensional Isolation System

Tomoyoshi Watakabe, Takahiro Okuda, Satoshi Okajima

Proc. ASME. PVP2022, Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division, V005T08A011, July 17–22, 2022

Paper No: PVP2022-85412

DOI: https://doi.org/10.1115/PVP2022-85412

View Paper

Topics: Pipes, Sodium fast reactors

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

Paper No: PVP2021-61942

DOI: https://doi.org/10.1115/PVP2021-61942

View Paper

Topics: Fast neutron reactors, Fracture (Materials), In-service inspection, Leakage, Leak-before-break, Sodium, Sodium fast reactors

Proceedings Papers

Research and Development of Three-Dimensional Isolation System for Sodium-Cooled Fast Reactor: Part 5 — Isolation Performance Applied to Reactor Building

Takahiro Somaki, Tsuyoshi Fukasawa, Shigeki Okamura, Takayuki Miyagawa, Masato Uchita, Tomohiko Yamamoto, Masashi Miyazaki, Satoshi Fujita

Proc. ASME. PVP2020, Volume 9: Seismic Engineering, V009T09A019, August 3, 2020

Paper No: PVP2020-21709

DOI: https://doi.org/10.1115/PVP2020-21709

View Paper

Topics: Industrial research, Sodium fast reactors

Proceedings Papers

Research and Development of Three-Dimensional Isolation System for Sodium-Cooled Fast Reactor: Part 6 — Development of High Speed Oil Damper for Isolated Building

Tsuyoshi Fukasawa, Takahiro Somaki, Takayuki Miyagawa, Masato Uchita, Tomohiko Yamamoto, Masashi Miyazaki, Shigeki Okamura, Satoshi Fujita

Proc. ASME. PVP2020, Volume 9: Seismic Engineering, V009T09A018, August 3, 2020

Paper No: PVP2020-21320

DOI: https://doi.org/10.1115/PVP2020-21320

View Paper

Topics: Dampers, Industrial research, Sodium fast reactors

Proceedings Papers

Research and Development of Three-Dimensional Isolation System for Sodium-Cooled Fast Reactor: Part 3 — Characteristics for Elements on Basis of Half-Scale Loading Tests

Takahiro Somaki, Tsuyoshi Fukasawa, Shigeki Okamura, Takayuki Miyagawa, Masato Uchita, Tomohiko Yamamoto, Tomoyoshi Watakabe, Satoshi Fujita

Proc. ASME. PVP2019, Volume 8: Seismic Engineering, V008T08A037, July 14–19, 2019

Paper No: PVP2019-93475

DOI: https://doi.org/10.1115/PVP2019-93475

View Paper

Topics: Bearings, Disks, Industrial research, Rubber, Sodium fast reactors, Springs, Dampers, Design methodology, Displacement, Dynamic testing (Materials)

Proceedings Papers

Research and Development of Three-Dimensional Isolation System for Sodium-Cooled Fast Reactor: Part 4 — Proposal of Optimal Combination Method for Disc Spring Units and Newly Friction Model for Sliding Elements

Tsuyoshi Fukasawa, Shigeki Okamura, Takahiro Somaki, Takayuki Miyagawa, Masato Uchita, Tomohiko Yamamoto, Tomoyoshi Watakabe, Satoshi Fujita

Proc. ASME. PVP2019, Volume 8: Seismic Engineering, V008T08A038, July 14–19, 2019

Paper No: PVP2019-93480

DOI: https://doi.org/10.1115/PVP2019-93480

View Paper

Topics: Disks, Friction, Industrial research, Sodium fast reactors, Springs, Algorithms, Bearings, Dampers, Dimensions, Quality control

Proceedings Papers

Hot Cell Pulsed Laser Welding of Neutron Irradiated Type 304 Stainless Steel With a Maximum Damage Dose of 28 DPA

Paula D. Freyer, Jonathan K. Tatman, Frank A. Garner, Greg J. Frederick, Benjamin J. Sutton

Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A087, July 14–19, 2019

Paper No: PVP2019-93316

DOI: https://doi.org/10.1115/PVP2019-93316

View Paper

Topics: Damage, Laser welding, Neutrons, Stainless steel, Helium, Welding, Heat, Welded joints, Cracking (Materials), Fracture (Process)

Proceedings Papers

Advances Towards Elastic-Perfectly Plastic Simulation of the Core of Printed Circuit Heat Exchangers

Alon Katz, Devesh Ranjan

Proc. ASME. PVP2019, Volume 3: Design and Analysis, V003T03A093, July 14–19, 2019

Paper No: PVP2019-93807

DOI: https://doi.org/10.1115/PVP2019-93807

View Paper

Topics: Circuits, Heat exchangers, Simulation, Stress, Algorithms, ASME Standards, Brayton cycle, Computer simulation, Computer software, Coolants

Proceedings Papers

Creep-Fatigue Damage Evaluation of Grade 91 Steel Using Interrupt Creep Fatigue Test

Uijeong Ro, Jeong Hwan Kim, Hoomin Lee, Seok Jun Kang, Moon Ki Kim

Proc. ASME. PVP2018, Volume 1A: Codes and Standards, V01AT01A023, July 15–20, 2018

Paper No: PVP2018-84561

DOI: https://doi.org/10.1115/PVP2018-84561

View Paper

Topics: Creep, Damage, Fatigue, Fatigue testing, Steel, Testing, Nuclear power stations, Finite element model, Operating temperature, Pipes

Proceedings Papers

Research and Development of Three-Dimensional Isolation System for Sodium-Cooled Fast Reactor: Part 2 — Details of Characteristics for Disc Springs and Oil Dampers on Basis of Full-Scale Loading Tests

Takahiro Somaki, Tsuyoshi Fukasawa, Takayuki Miyagawa, Tomohiko Yamamoto, Yoshifumi Hibako, Masanari Okamoto, Osamu Noda, Futoshi Ishizuka

Proc. ASME. PVP2018, Volume 8: Seismic Engineering, V008T08A035, July 15–20, 2018

Paper No: PVP2018-84491

DOI: https://doi.org/10.1115/PVP2018-84491

View Paper

Topics: Dampers, Disks, Industrial research, Sodium fast reactors, Springs, Damping, Bearings, Rubber, Stress, Waves

Proceedings Papers

Research and Development of Three-Dimensional Isolation System for Sodium-Cooled Fast Reactor: Part 1 — Proposal of Analytical Models Based on Loading Tests

Tsuyoshi Fukasawa, Shigeki Okamura, Takahiro Somaki, Takayuki Miyagawa, Masato Uchita, Tomohiko Yamamoto, Tomoyoshi Watakabe, Satoshi Fujita

Proc. ASME. PVP2018, Volume 8: Seismic Engineering, V008T08A038, July 15–20, 2018

Paper No: PVP2018-84532

DOI: https://doi.org/10.1115/PVP2018-84532

View Paper

Topics: Bearings, Dampers, Damping, Design, Differential equations, Disks, Industrial research, Reactor vessels, Rubber, Sodium fast reactors

Proceedings Papers

Investigation Into Thermal Stress Characteristics of Pipe-in-Pipe Under High Temperature Condition

Si-Hwa Jeong, Min-Gu Won, Nam-Su Huh, Yun-Jae Kim, Young-Jin Oh, Jae-Boong Choi

Proc. ASME. PVP2018, Volume 3A: Design and Analysis, V03AT03A030, July 15–20, 2018

Paper No: PVP2018-84578

DOI: https://doi.org/10.1115/PVP2018-84578

View Paper

Topics: High temperature, Pipes, Thermal stresses, Geometry, Heat transfer, Sodium fast reactors, Temperature distribution, Boundary-value problems, Convection, Finite element 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

Paper No: PVP2017-65725

DOI: https://doi.org/10.1115/PVP2017-65725

View Paper

Topics: Boilers, Computer simulation, Coolants, Damping, Earthquakes, Engineering prototypes, Excitation, Fast neutron reactors, Fluid dynamics, Fluid structure interaction

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

Paper No: PVP2017-65727

DOI: https://doi.org/10.1115/PVP2017-65727

View Paper

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

Paper No: PVP2017-65601

DOI: https://doi.org/10.1115/PVP2017-65601

View Paper

Topics: Flow-induced vibrations, Numerical analysis, Pipes, Pressure, Design, Stress, Computer simulation, Flow (Dynamics), Construction, Cooling systems

Proceedings Papers

Development on Rubber Bearings for Sodium-Cooled Fast Reactor: Part 5 — Non-Linear Analytical Models for Thick Rubber Bearing

Tsutomu Hirotani, Takahiro Mori, Tsuyoshi Fukasawa, Shigeki Okamura, Tomohiko Yamamoto, Tomoyoshi Watakabe

Proc. ASME. PVP2017, Volume 8: Seismic Engineering, V008T08A046, July 16–20, 2017

Paper No: PVP2017-65655

DOI: https://doi.org/10.1115/PVP2017-65655

View Paper

Topics: Bearings, Rubber, Sodium fast reactors, Finite element methods, Finite element model, Springs, Elasticity, Finite element analysis, Shear (Mechanics), Thermal stresses

Proceedings Papers

Research and Development of Three Dimensional Seismic Isolation System Utilized Coned-Disc-Springs With Rubber Bearings

Takayuki Miyagawa, Tomoyoshi Watakabe, Tomohiko Yamamoto, Tsuyoshi Fukasawa, Shigeki Okamura

Proc. ASME. PVP2017, Volume 8: Seismic Engineering, V008T08A043, July 16–20, 2017

Paper No: PVP2017-65549

DOI: https://doi.org/10.1115/PVP2017-65549

View Paper

Topics: Bearings, Disks, Industrial research, Rubber, Springs, Sodium fast reactors, Stress, Buckling, Design, Reactor vessels

Proceedings Papers

Development on Rubber Bearings for Sodium-Cooled Fast Reactor: Part 6 — Proposal of New Type of Hysteresis Model for Ultimate Behavior

Tsuyoshi Fukasawa, Shigeki Okamura, Tomohiko Yamamoto, Tomoyoshi Watakabe

Proc. ASME. PVP2017, Volume 8: Seismic Engineering, V008T08A044, July 16–20, 2017

Paper No: PVP2017-65557

DOI: https://doi.org/10.1115/PVP2017-65557

View Paper

Topics: Bearings, Rubber, Sodium fast reactors, Design, Differential equations, Deformation, Earthquakes, Probabilistic risk assessment, Risk

Proceedings Papers

Numerical Analysis of Unsteady Phenomena in Upper Plenum and Hot-Leg Piping System of Advanced Loop-Type Sodium Cooled Fast Reactor

Shigeru Takaya, Tatsuya Fujisaki, Masaaki Tanaka

Proc. ASME. PVP2016, Volume 3: Design and Analysis, V003T03A003, July 17–21, 2016

Paper No: PVP2016-63845

DOI: https://doi.org/10.1115/PVP2016-63845

View Paper

Topics: Numerical analysis, Piping systems, Sodium fast reactors, Flow (Dynamics), Pipes, Design, Simulation results, Swirling flow, Computer simulation, Construction

Proceedings Papers

Consideration of Irradiation Effect in Components Design: Illustration of a Way to Introduce an Environmental Effect in the Design Process

C. Pétesch, T. Lebarbé, C. Pascal, S. Dubiez-Le Goff

Proc. ASME. PVP2016, Volume 3: Design and Analysis, V003T03A040, July 17–21, 2016

Paper No: PVP2016-63567

DOI: https://doi.org/10.1115/PVP2016-63567

View Paper

Topics: Design, Irradiation (Radiation exposure), Damage, Sodium fast reactors, Breeder reactors, Creep, Fatigue damage, Fusion reactors, High temperature, Pressure

2 3 4

NARROW

Seismic Assessment of Crossover Piping on a Sodium Cooled Fast Reactor With Three-Dimensional Isolation System

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

Research and Development of Three-Dimensional Isolation System for Sodium-Cooled Fast Reactor: Part 5 — Isolation Performance Applied to Reactor Building

Research and Development of Three-Dimensional Isolation System for Sodium-Cooled Fast Reactor: Part 6 — Development of High Speed Oil Damper for Isolated Building

Research and Development of Three-Dimensional Isolation System for Sodium-Cooled Fast Reactor: Part 3 — Characteristics for Elements on Basis of Half-Scale Loading Tests

Research and Development of Three-Dimensional Isolation System for Sodium-Cooled Fast Reactor: Part 4 — Proposal of Optimal Combination Method for Disc Spring Units and Newly Friction Model for Sliding Elements

Hot Cell Pulsed Laser Welding of Neutron Irradiated Type 304 Stainless Steel With a Maximum Damage Dose of 28 DPA

Advances Towards Elastic-Perfectly Plastic Simulation of the Core of Printed Circuit Heat Exchangers

Creep-Fatigue Damage Evaluation of Grade 91 Steel Using Interrupt Creep Fatigue Test

Research and Development of Three-Dimensional Isolation System for Sodium-Cooled Fast Reactor: Part 2 — Details of Characteristics for Disc Springs and Oil Dampers on Basis of Full-Scale Loading Tests

Research and Development of Three-Dimensional Isolation System for Sodium-Cooled Fast Reactor: Part 1 — Proposal of Analytical Models Based on Loading Tests

Investigation Into Thermal Stress Characteristics of Pipe-in-Pipe Under High Temperature Condition

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

Fluid Structure Interaction for Tubes Bundles: Different Homogenization Methods

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

Development on Rubber Bearings for Sodium-Cooled Fast Reactor: Part 5 — Non-Linear Analytical Models for Thick Rubber Bearing

Research and Development of Three Dimensional Seismic Isolation System Utilized Coned-Disc-Springs With Rubber Bearings

Development on Rubber Bearings for Sodium-Cooled Fast Reactor: Part 6 — Proposal of New Type of Hysteresis Model for Ultimate Behavior

Numerical Analysis of Unsteady Phenomena in Upper Plenum and Hot-Leg Piping System of Advanced Loop-Type Sodium Cooled Fast Reactor

Consideration of Irradiation Effect in Components Design: Illustration of a Way to Introduce an Environmental Effect in the Design Process

Journals

Conference Proceedings

eBooks

Resources

Opportunities

Journals

Conference Proceedings

eBooks

Resources

Opportunities

This Feature Is Available To Subscribers Only