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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

Paper No: PVP2021-62845

DOI: https://doi.org/10.1115/PVP2021-62845

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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

Paper No: PVP2021-61942

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

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

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

Paper No: PVP2020-21491

DOI: https://doi.org/10.1115/PVP2020-21491

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Topics: Anisotropy, Buckling, Shells, Plates (structures), Displacement, Constitutive equations, Deformation, High temperature, Modeling, Risk

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

Paper No: PVP2020-21720

DOI: https://doi.org/10.1115/PVP2020-21720

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Topics: Compression, Creep, Design, Displacement, Engineering standards, Fatigue, Fatigue testing, Generation IV reactors, High temperature, Sodium

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

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

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

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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

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

Paper No: PVP2018-84471

DOI: https://doi.org/10.1115/PVP2018-84471

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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

Paper No: PVP2018-84098

DOI: https://doi.org/10.1115/PVP2018-84098

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Topics: Excitation, Fast neutron reactors, Numerical analysis, Fluids, Fuels, Sodium, Boundary-value problems, Computers, Coolants, Design

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

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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

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

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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

Paper No: PVP2015-45862

DOI: https://doi.org/10.1115/PVP2015-45862

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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

Paper No: PVP2015-45461

DOI: https://doi.org/10.1115/PVP2015-45461

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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

Paper No: PVP2015-45904

DOI: https://doi.org/10.1115/PVP2015-45904

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Topics: Experimental analysis, Fluid dynamics, Fluid structure interaction, Manufacturing, Vibration, Breeder reactors, Computer simulation, Containment, Damping, Displacement

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

Paper No: PVP2014-28324

DOI: https://doi.org/10.1115/PVP2014-28324

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Topics: Damage, Design, Stress, Creep, Boilers, Construction, Cylinders, Membranes, Sodium, Stainless steel

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

Paper No: PVP2014-28485

DOI: https://doi.org/10.1115/PVP2014-28485

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Topics: Design, Engineering prototypes, Feedback, Sodium, Sodium fast reactors, Vacuum, Vessels

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

Paper No: PVP2014-28918

DOI: https://doi.org/10.1115/PVP2014-28918

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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

Paper No: PVP2014-28366

DOI: https://doi.org/10.1115/PVP2014-28366

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Topics: Design, Flanges, High temperature, Nuclear power stations, Sodium, Construction, Fusion reactors, Low temperature, Pipes, Pressure

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

Paper No: PVP2014-28053

DOI: https://doi.org/10.1115/PVP2014-28053

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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

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

Paper No: PVP2013-97608

DOI: https://doi.org/10.1115/PVP2013-97608

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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

Paper No: PVP2013-97611

DOI: https://doi.org/10.1115/PVP2013-97611

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Topics: Construction, Design, Fast neutron reactors, JSME Standards, Steel, Strength (Materials), Creep, Boilers, Circuits, Coolants

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NARROW

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

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

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

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

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

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

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

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

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

Fluid Structure Interaction for Tubes Bundles: Different Homogenization Methods

Core Mechanical Dynamics Experiment in the Phénix Reactor

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

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

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

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

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

RCC-MRx Edition 2012: Bolt Design Rules Criteria

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

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

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

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