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Proceedings Papers

Progress of EASICS Validation Experiments and Code Comparison of R5, RCC-MRX and ASME III Division V

Peter James, David Coon, Colin Austin, Nicholas Underwood, Caroline Meek, Marc Chevalier, David Dean
Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A031, July 13–15, 2021
Publisher: American Society of Mechanical Engineers
Paper No: PVP2021-62845
https://doi.org/10.1115/PVP2021-62845
View Paper titled, Progress of EASICS Validation Experiments and Code Comparison of R5, RCC-MRX and ASME III Division V
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Topics: Compression, Creep, Design, Displacement, Engineering standards, Fatigue, Fatigue testing, Generation IV reactors, High temperature, Pipes
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
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Topics: Fast neutron reactors, Fracture (Materials), In-service inspection, Leakage, Leak-before-break, Sodium, Sodium fast reactors
Proceedings Papers

Overview of EASICS Validation Experiments and Code Comparison of R5, RCC-MRX and ASME III Division V

Peter James, David Coon, Colin Austin, Nicholas Underwood, Marc Chevalier, David Dean
Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A093, August 3, 2020
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21720
https://doi.org/10.1115/PVP2020-21720
View Paper titled, Overview of EASICS Validation Experiments and Code Comparison of R5, RCC-MRX and ASME III Division V
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Topics: Compression, Creep, Design, Displacement, Engineering standards, Fatigue, Fatigue testing, Generation IV reactors, High temperature, Sodium
Proceedings Papers

Elasto-Visco-Plastic Buckling of Thick Anisotropic Shells: Numerical Buckling Predictions and Experiments

Nicolas Jacquet, Nicolas Tardif, Thomas Elguedj, Christophe Garnier
Proc. ASME. PVP2020, Volume 3: Design and Analysis, V003T03A070, August 3, 2020
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21491
https://doi.org/10.1115/PVP2020-21491
View Paper titled, Elasto-Visco-Plastic Buckling of Thick Anisotropic Shells: Numerical Buckling Predictions and Experiments
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Topics: Anisotropy, Buckling, Shells, Plates (structures), Displacement, Constitutive equations, Deformation, High temperature, Modeling, Risk
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
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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
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Topics: Excitation, Fast neutron reactors, Numerical analysis, Fluids, Fuels, Sodium, Boundary-value problems, Computers, Coolants, Design
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
Publisher: American Society of Mechanical Engineers
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

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
Publisher: American Society of Mechanical Engineers
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

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
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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
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
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Topics: Fluid structure interaction, Fluids, Fluid dynamics, Damping, Excitation, Fast neutron reactors, Sodium, Theoretical analysis, Boilers, Computer simulation
Proceedings Papers

Core Mechanical Dynamics Experiment in the Phénix Reactor

Daniel Broc, Jérome Cardolaccia, Laurent Martin, Jean Louis Portier
Proc. ASME. PVP2015, Volume 4: Fluid-Structure Interaction, V004T04A045, July 19–23, 2015
Publisher: American Society of Mechanical Engineers
Paper No: PVP2015-45862
https://doi.org/10.1115/PVP2015-45862
View Paper titled, Core Mechanical Dynamics Experiment in the Phénix Reactor
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Topics: Coolants, Damping, Design, Dynamic response, Dynamics (Mechanics), Engineering prototypes, Excitation, Fast neutron reactors, Fluids, Fuels
Proceedings Papers

Estimation of Elastic Crack Opening Displacement for Thin Elbows With Circumferential Through-Wall Cracks

Min-Kyu Kim, Han-Bum Surh, Min-Gu Won, Nam-Su Huh, Moon-Ki Kim, Jae-Boong Choi
Proc. ASME. PVP2015, Volume 6A: Materials and Fabrication, V06AT06A080, July 19–23, 2015
Publisher: American Society of Mechanical Engineers
Paper No: PVP2015-45461
https://doi.org/10.1115/PVP2015-45461
View Paper titled, Estimation of Elastic Crack Opening Displacement for Thin Elbows With Circumferential Through-Wall Cracks
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Topics: Displacement, Fracture (Materials), Pipes, Design, Finite element analysis, Leakage, Leak-before-break, Nuclear power stations, Sodium, Sodium fast reactors
Proceedings Papers

3D Effects in Fluid Flow During 2D Vibrations: Experimental Analysis of FSI for an Enclosed Hexagonal Assembly

Lucia Sargentini, Benjamin Cariteau, Jean-Paul Magnaud, Arnault Monavon, Gianluca Artini
Proc. ASME. PVP2015, Volume 4: Fluid-Structure Interaction, V004T04A046, July 19–23, 2015
Publisher: American Society of Mechanical Engineers
Paper No: PVP2015-45904
https://doi.org/10.1115/PVP2015-45904
View Paper titled, 3D Effects in Fluid Flow During 2D Vibrations: Experimental Analysis of FSI for an Enclosed Hexagonal Assembly
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Topics: Experimental analysis, Fluid dynamics, Fluid structure interaction, Manufacturing, Vibration, Breeder reactors, Computer simulation, Containment, Damping, Displacement
Proceedings Papers

Experimental and Numerical Analysis for Fluid-Structure Interaction for an Enclosed Hexagonal Assembly

Lucia Sargentini, Benjamin Cariteau, Morena Angelucci
Proc. ASME. PVP2014, Volume 5: High-Pressure Technology; ASME NDE Division; 22nd Scavuzzo Student Paper Symposium and Competition, V005T11A002, July 20–24, 2014
Publisher: American Society of Mechanical Engineers
Paper No: PVP2014-28053
https://doi.org/10.1115/PVP2014-28053
View Paper titled, Experimental and Numerical Analysis for Fluid-Structure Interaction for an Enclosed Hexagonal Assembly
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Topics: Fluid structure interaction, Manufacturing, Numerical analysis, Evacuations, Compacting, Engineering simulation, Fast neutron reactors, Flow (Dynamics), Free vibrations, Navier-Stokes equations
Proceedings Papers

Design Rules for Ratcheting Damage in AFCEN RCC-MRX 2012 Code

P. Lamagnère, Y. Lejeail, C. Petesch, T. Lebarbé, P. Matheron, S. Taheri, A. Martin
Proc. ASME. PVP2014, Volume 1: Codes and Standards, V001T01A061, July 20–24, 2014
Publisher: American Society of Mechanical Engineers
Paper No: PVP2014-28324
https://doi.org/10.1115/PVP2014-28324
View Paper titled, Design Rules for Ratcheting Damage in AFCEN RCC-MRX 2012 Code
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Topics: Damage, Design, Stress, Creep, Boilers, Construction, Cylinders, Membranes, Sodium, Stainless steel
Proceedings Papers

Physical and Numerical Methods for the Dynamic Behavior of the Fast Reactor Cores

Daniel Broc, Jérome Cardolaccia, Laurent Martin
Proc. ASME. PVP2014, Volume 4: Fluid-Structure Interaction, V004T04A076, July 20–24, 2014
Publisher: American Society of Mechanical Engineers
Paper No: PVP2014-28918
https://doi.org/10.1115/PVP2014-28918
View Paper titled, Physical and Numerical Methods for the Dynamic Behavior of the Fast Reactor Cores
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Topics: Fast neutron reactors, Numerical analysis, Fluids, Sodium, Computers, Fluid structure interaction, Coolants, Design, Excitation, Fuels
Proceedings Papers

RCC-MRx Edition 2012: Bolt Design Rules Criteria

C. Borazzo, C. Pétesch, T. Lebarbé, O. Ancelet
Proc. ASME. PVP2014, Volume 3: Design and Analysis, V003T03A017, July 20–24, 2014
Publisher: American Society of Mechanical Engineers
Paper No: PVP2014-28366
https://doi.org/10.1115/PVP2014-28366
View Paper titled, RCC-MRx Edition 2012: Bolt Design Rules Criteria
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Topics: Design, Flanges, High temperature, Nuclear power stations, Sodium, Construction, Fusion reactors, Low temperature, Pipes, Pressure
Proceedings Papers

Consistency Between Evolution of Codified Rules and SFR Prototype Development: Astrid and RCC-MRX Example

M. Blanc, C. Pétesch, O. Gélineau, T. Lebarbé, M. Blat-Yrieix
Proc. ASME. PVP2014, Volume 1: Codes and Standards, V001T01A062, July 20–24, 2014
Publisher: American Society of Mechanical Engineers
Paper No: PVP2014-28485
https://doi.org/10.1115/PVP2014-28485
View Paper titled, Consistency Between Evolution of Codified Rules and SFR Prototype Development: Astrid and RCC-MRX Example
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Topics: Design, Engineering prototypes, Feedback, Sodium, Sodium fast reactors, Vacuum, Vessels
Proceedings Papers

Development of 2012 Edition of JSME Code for Design and Construction of Fast Reactors: (2) Development of the Material Strength Standard of 316FR Stainless Steel

Takashi Onizawa, Yuji Nagae, Shigeru Takaya, Tai Asayama
Proc. ASME. PVP2013, Volume 1B: Codes and Standards, V01BT01A034, July 14–18, 2013
Publisher: American Society of Mechanical Engineers
Paper No: PVP2013-97608
https://doi.org/10.1115/PVP2013-97608
View Paper titled, Development of 2012 Edition of JSME Code for Design and Construction of Fast Reactors: (2) Development of the Material Strength Standard of 316FR Stainless Steel
Open the PDF for Development of 2012 Edition of JSME Code for Design and Construction of Fast Reactors: (2) Development of the Material Strength Standard of 316FR Stainless Steel in another window
Topics: Construction, Design, Fast neutron reactors, JSME Standards, Stainless steel, Strength (Materials), Creep, Irradiation (Radiation exposure), Japan Society of Mechanical Engineers, Low cycle fatigue
Proceedings Papers

Development of 2012 Edition of JSME Code for Design and Construction of Fast Reactors: (3) Development of the Material Strength Standard of Modified 9Cr-1Mo Steel

Takashi Onizawa, Yuji Nagae, Shigeru Takaya, Tai Asayama
Proc. ASME. PVP2013, Volume 1B: Codes and Standards, V01BT01A036, July 14–18, 2013
Publisher: American Society of Mechanical Engineers
Paper No: PVP2013-97611
https://doi.org/10.1115/PVP2013-97611
View Paper titled, Development of 2012 Edition of JSME Code for Design and Construction of Fast Reactors: (3) Development of the Material Strength Standard of Modified 9Cr-1Mo Steel
Open the PDF for Development of 2012 Edition of JSME Code for Design and Construction of Fast Reactors: (3) Development of the Material Strength Standard of Modified 9Cr-1Mo Steel in another window
Topics: Construction, Design, Fast neutron reactors, JSME Standards, Steel, Strength (Materials), Creep, Boilers, Circuits, Coolants