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Proceedings Papers

Implementing Probabilistic Design Methods in Plant Systems Design

J. Adin Mann, Ben Pellereau, Mihai A. Diaconeasa, Michael Martin, Nawal K. Prinja

Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A061, July 17–22, 2022

Paper No: PVP2022-84743

DOI: https://doi.org/10.1115/PVP2022-84743

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Topics: Cycles, Design, Design methodology, Failure mechanisms

Proceedings Papers

Comparison of Technical Standards Between Buried and Above Ground Polyethylene Pipe in the Application of Nuclear Power Plant

Jianfeng Shi, Yuhua Cao, Di Jiao, Fa Yu, Yu Li, Jiayin Jiang, Jinyang Zheng

Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A006, July 17–22, 2022

Paper No: PVP2022-84477

DOI: https://doi.org/10.1115/PVP2022-84477

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Topics: Design, Design methodology, Engineering standards, Nuclear power stations, Pipes, Polyethylene pipes, Stress, Water, Cooling, Pipelines

Proceedings Papers

Design Charts for an Integrated Creep-Fatigue Damage Evaluation Approach

B. Barua, M. C. Messner, T.-L. Sham

Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A062, July 17–22, 2022

Paper No: PVP2022-84807

DOI: https://doi.org/10.1115/PVP2022-84807

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Topics: Creep, Damage, Design, Fatigue, High temperature, Alloys, Design methodology, Failure data, Fatigue damage, Nuclear reactors

Proceedings Papers

Simplified Criteria With Reduced Testing Effort for Selecting Clad Materials for High Temperature Reactor Structural Components

B. Barua, R. I. Jetter, M. C. Messner, T.-L. Sham

Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A037, July 13–15, 2021

Paper No: PVP2021-61858

DOI: https://doi.org/10.1115/PVP2021-61858

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Topics: High temperature, Structural elements (Construction), Testing, Creep, Design, Temperature, Alloys, Corrosion, Corrosion resistant materials, Design methodology

Proceedings Papers

Validation of Modern Finite Analysis Methods for Glassy Polymers Using Historical Studies

Bart Kemper

Proc. ASME. PVP2021, Volume 2: Computer Technology and Bolted Joints; Design and Analysis, V002T03A025, July 13–15, 2021

Paper No: PVP2021-62146

DOI: https://doi.org/10.1115/PVP2021-62146

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Topics: Design, Design methodology, Dimensions, Finite element analysis, Geometry, Polymers, Pressure vessels, Safety, Shapes, Thin wall structures

Proceedings Papers

Research on Design Method of Hydrogen Storage Pressure Vessel in the Hydrogen Refueling Station Based on Failure Mode

Fang Ji, Xiaoliang Jia, Zhiwei Chen, Cenfan Liu, Linlin Duan

Proc. ASME. PVP2021, Volume 2: Computer Technology and Bolted Joints; Design and Analysis, V002T03A020, July 13–15, 2021

Paper No: PVP2021-61901

DOI: https://doi.org/10.1115/PVP2021-61901

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Topics: Design methodology, Failure mechanisms, Hydrogen, Hydrogen storage, Pressure vessels

Proceedings Papers

Utilisation Limits of 1¼Cr½Mo (SA387-11-2) Steel in High Plate Thickness

Ingo Detemple, Bastian Philippi, Jörg Maffert

Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A061, August 3, 2020

Paper No: PVP2020-21461

DOI: https://doi.org/10.1115/PVP2020-21461

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Topics: Steel, Construction, Design, Petrochemicals, Design methodology, Mechanical properties, Operating temperature, Pressure vessels

Proceedings Papers

Overview of UK Policy and Research Landscape Relevant to Deploying Advanced Nuclear Technologies in the UK

Nicholas Underwood, Paul Nevitt, Andrew Howarth, Nicholas Barron

Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A043, August 3, 2020

Paper No: PVP2020-21790

DOI: https://doi.org/10.1115/PVP2020-21790

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Topics: Advanced materials, Boiling, Carbon, Climate change, Construction, Cooling, Cooling systems, Cutting, Cycles, Design

Proceedings Papers

Development of Design Method for High Temperature Nuclear Reactor Cladded Components

B. Barua, M. C. Messner, R. I. Jetter, T.-L. Sham

Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A067, August 3, 2020

Paper No: PVP2020-21469

DOI: https://doi.org/10.1115/PVP2020-21469

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Topics: Design methodology, High temperature, Nuclear reactors, Design, Coolants, Corrosion resistant materials, Corrosion, Creep, Failure, Finite element analysis

Proceedings Papers

A High Temperature Primary Load Design Method Based on Elastic Perfectly-Plastic and Simplified Inelastic Analysis

M. C. Messner, R. I. Jetter, T.-L. Sham

Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A068, August 3, 2020

Paper No: PVP2020-21470

DOI: https://doi.org/10.1115/PVP2020-21470

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Topics: Design methodology, High temperature, Inelastic analysis, Stress, Creep, Design, Damage, Finite element analysis, ASME Boiler and Pressure Vessel Code, Computer software

Proceedings Papers

Selection Criteria for Clad Materials to Use With a 316H Base Material for High Temperature Nuclear Reactor Cladded Components

B. Barua, M. C. Messner, R. I. Jetter, T.-L. Sham

Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A070, August 3, 2020

Paper No: PVP2020-21493

DOI: https://doi.org/10.1115/PVP2020-21493

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Topics: High temperature, Nuclear reactors, Creep, Design, Alloys, Temperature, Cladding systems (Building), Design methodology, Elastic moduli, Failure

Proceedings Papers

Acceptance Criteria for the Mechanical Integrity of Clad/Base Metal Interface for High Temperature Nuclear Reactor Cladded Components

B. Barua, M. C. Messner, A. Rovinelli, T.-L. Sham

Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A071, August 3, 2020

Paper No: PVP2020-21494

DOI: https://doi.org/10.1115/PVP2020-21494

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Topics: Acceptance criteria, Base metals, High temperature, Nuclear reactors, Design, Shear stress, Temperature, Design methodology, Bonding, Corrosion resistance

Proceedings Papers

A New Method for Preventing Plastic Collapse of Ellipsoidal Head Under Internal Pressure

Keming Li, Jinyang Zheng, Zekun Zhang, Chaohua Gu, Ping Xu

Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A083, August 3, 2020

Paper No: PVP2020-21212

DOI: https://doi.org/10.1115/PVP2020-21212

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Topics: Collapse, Design methodology, Pressure, Pressure vessels

Proceedings Papers

Comparative Evaluation of Plastic Design Methods for Fatigue Assessment of a Nuclear Class 1 Piping Nozzle

David M. Clarkson, Christopher D. Bell, Donald Mackenzie

Proc. ASME. PVP2020, Volume 3: Design and Analysis, V003T03A043, August 3, 2020

Paper No: PVP2020-21271

DOI: https://doi.org/10.1115/PVP2020-21271

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Topics: Design methodology, Fatigue, Nozzles, Pipes, Design, Finite element analysis, ASME Boiler and Pressure Vessel Code, Pressurized water reactors, Stress, Coolants

Proceedings Papers

Robust Design Approach to 2 Inch and 3 Inch Thermal Tees on 14 Inch Pipework for Hot and Cold Fluid Turbulent Mixing at the Branch-Run Interface

Phil Wallace

Proc. ASME. PVP2020, Volume 3: Design and Analysis, V003T03A021, August 3, 2020

Paper No: PVP2020-21847

DOI: https://doi.org/10.1115/PVP2020-21847

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Topics: Design, Fatigue, Fluids, Piping systems, Turbulence, Stress, Computational fluid dynamics, Design methodology, Fatigue life, Finite element analysis

Proceedings Papers

A Case Study: Balanced Globe Valve Load Sensitive Behavior Upon Opening

Ronald Farrell, Preston Vock

Proc. ASME. PVP2020, Volume 8: Operations, Applications, and Components, V008T08A017, August 3, 2020

Paper No: PVP2020-21289

DOI: https://doi.org/10.1115/PVP2020-21289

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Topics: Stress, Valves, Engines, Motors, Flow (Dynamics), Actuators, Disks, Switches, Torque, Design

Proceedings Papers

A Unified Engineering Inelastic Model for 316H Stainless Steel

V.-T. Phan, M. C. Messner, T.-L. Sham

Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A040, July 14–19, 2019

Paper No: PVP2019-93641

DOI: https://doi.org/10.1115/PVP2019-93641

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Topics: Boilers, Constitutive equations, Creep, Deformation, Design, Design methodology, High temperature, High temperature materials, Inelastic analysis, Plasticity

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

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

Proceedings Papers

The Fundamental Mechanical Characteristics Evaluation for Bolted Pipe Flange Connections With RTJ Gaskets Under Internal Pressure

Kenshiro Nakade, Koji Sato, Toshiyuki Sawa

Proc. ASME. PVP2019, Volume 2: Computer Technology and Bolted Joints, V002T02A013, July 14–19, 2019

Paper No: PVP2019-93489

DOI: https://doi.org/10.1115/PVP2019-93489

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Topics: Flange connections, Gaskets, Mechanical properties, Pipes, Pressure, Stress, Leakage, Deformation, Sealing (Process), Aluminum

Proceedings Papers

A New Design Method for Axially Loaded Thin-Walled Cylindrical Shells Based on Elasto-Plastic Buckling Analysis

Peng Jiao, Zhiping Chen, He Ma

Proc. ASME. PVP2019, Volume 3: Design and Analysis, V003T03A077, July 14–19, 2019

Paper No: PVP2019-93233

DOI: https://doi.org/10.1115/PVP2019-93233

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Topics: Buckling, Design methodology, Pipes, Stress

NARROW

Implementing Probabilistic Design Methods in Plant Systems Design

Comparison of Technical Standards Between Buried and Above Ground Polyethylene Pipe in the Application of Nuclear Power Plant

Design Charts for an Integrated Creep-Fatigue Damage Evaluation Approach

Simplified Criteria With Reduced Testing Effort for Selecting Clad Materials for High Temperature Reactor Structural Components

Validation of Modern Finite Analysis Methods for Glassy Polymers Using Historical Studies

Research on Design Method of Hydrogen Storage Pressure Vessel in the Hydrogen Refueling Station Based on Failure Mode

Utilisation Limits of 1¼Cr½Mo (SA387-11-2) Steel in High Plate Thickness

Overview of UK Policy and Research Landscape Relevant to Deploying Advanced Nuclear Technologies in the UK

Development of Design Method for High Temperature Nuclear Reactor Cladded Components

A High Temperature Primary Load Design Method Based on Elastic Perfectly-Plastic and Simplified Inelastic Analysis

Selection Criteria for Clad Materials to Use With a 316H Base Material for High Temperature Nuclear Reactor Cladded Components

Acceptance Criteria for the Mechanical Integrity of Clad/Base Metal Interface for High Temperature Nuclear Reactor Cladded Components

A New Method for Preventing Plastic Collapse of Ellipsoidal Head Under Internal Pressure

Comparative Evaluation of Plastic Design Methods for Fatigue Assessment of a Nuclear Class 1 Piping Nozzle

Robust Design Approach to 2 Inch and 3 Inch Thermal Tees on 14 Inch Pipework for Hot and Cold Fluid Turbulent Mixing at the Branch-Run Interface

A Case Study: Balanced Globe Valve Load Sensitive Behavior Upon Opening

A Unified Engineering Inelastic Model for 316H Stainless Steel

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

The Fundamental Mechanical Characteristics Evaluation for Bolted Pipe Flange Connections With RTJ Gaskets Under Internal Pressure

A New Design Method for Axially Loaded Thin-Walled Cylindrical Shells Based on Elasto-Plastic Buckling Analysis

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