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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
https://doi.org/10.1115/PVP2022-85412
View Paper titled, Seismic Assessment of Crossover Piping on a Sodium Cooled Fast Reactor With Three-Dimensional Isolation System
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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
https://doi.org/10.1115/PVP2021-61942
View Paper titled, Development of Leak Before Break Assessment Guidelines for Sodium Cooled Fast Reactors in Japan
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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
https://doi.org/10.1115/PVP2020-21709
View Paper titled, Research and Development of Three-Dimensional Isolation System for Sodium-Cooled Fast Reactor: Part 5 — Isolation Performance Applied to Reactor Building
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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
https://doi.org/10.1115/PVP2020-21320
View Paper titled, Research and Development of Three-Dimensional Isolation System for Sodium-Cooled Fast Reactor: Part 6 — Development of High Speed Oil Damper for Isolated Building
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Topics: Dampers, Industrial research, Sodium fast reactors
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
https://doi.org/10.1115/PVP2019-93316
View Paper titled, Hot Cell Pulsed Laser Welding of Neutron Irradiated Type 304 Stainless Steel With a Maximum Damage Dose of 28 DPA
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Topics: Damage, Laser welding, Neutrons, Stainless steel, Helium, Welding, Heat, Welded joints, Cracking (Materials), Fracture (Process)
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
https://doi.org/10.1115/PVP2019-93475
View Paper titled, 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
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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
https://doi.org/10.1115/PVP2019-93480
View Paper titled, 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
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Topics: Disks, Friction, Industrial research, Sodium fast reactors, Springs, Algorithms, Bearings, Dampers, Dimensions, Quality control
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
https://doi.org/10.1115/PVP2019-93807
View Paper titled, Advances Towards Elastic-Perfectly Plastic Simulation of the Core of Printed Circuit Heat Exchangers
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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
https://doi.org/10.1115/PVP2018-84561
View Paper titled, Creep-Fatigue Damage Evaluation of Grade 91 Steel Using Interrupt Creep Fatigue Test
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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
https://doi.org/10.1115/PVP2018-84491
View Paper titled, 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
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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
https://doi.org/10.1115/PVP2018-84532
View Paper titled, Research and Development of Three-Dimensional Isolation System for Sodium-Cooled Fast Reactor: Part 1 — Proposal of Analytical Models Based on Loading Tests
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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
https://doi.org/10.1115/PVP2018-84578
View Paper titled, Investigation Into Thermal Stress Characteristics of Pipe-in-Pipe Under High Temperature Condition
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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
https://doi.org/10.1115/PVP2017-65725
View Paper titled, Fluid Structure Interaction for Tubes Bundles: Presentation of a Linear Equivalent Model
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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
https://doi.org/10.1115/PVP2017-65727
View Paper titled, Fluid Structure Interaction for Tubes Bundles: Different Homogenization Methods
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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
https://doi.org/10.1115/PVP2017-65601
View Paper titled, Numerical Analysis of Flow-Induced Vibration of Large Diameter Pipe With Short Elbow
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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
https://doi.org/10.1115/PVP2017-65655
View Paper titled, Development on Rubber Bearings for Sodium-Cooled Fast Reactor: Part 5 — Non-Linear Analytical Models for Thick Rubber Bearing
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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
https://doi.org/10.1115/PVP2017-65549
View Paper titled, Research and Development of Three Dimensional Seismic Isolation System Utilized Coned-Disc-Springs With Rubber Bearings
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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
https://doi.org/10.1115/PVP2017-65557
View Paper titled, Development on Rubber Bearings for Sodium-Cooled Fast Reactor: Part 6 — Proposal of New Type of Hysteresis Model for Ultimate Behavior
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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
https://doi.org/10.1115/PVP2016-63845
View Paper titled, Numerical Analysis of Unsteady Phenomena in Upper Plenum and Hot-Leg Piping System of Advanced Loop-Type Sodium Cooled Fast Reactor
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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
https://doi.org/10.1115/PVP2016-63567
View Paper titled, Consideration of Irradiation Effect in Components Design: Illustration of a Way to Introduce an Environmental Effect in the Design Process
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Topics: Design, Irradiation (Radiation exposure), Damage, Sodium fast reactors, Breeder reactors, Creep, Fatigue damage, Fusion reactors, High temperature, Pressure