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Proceedings Papers

Probabilistic Structural Integrity Analysis for Advanced Modular Reactors

James M. Finley, Henry Cathcart
Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A051, July 17–22, 2022
Paper No: PVP2022-81135
DOI: https://doi.org/10.1115/PVP2022-81135
View Paper titled, Probabilistic Structural Integrity Analysis for Advanced Modular Reactors
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Topics: Creep, Damage, Design, Emissions, High temperature, Nuclear reactors, Reliability, Robustness, Safety, Uncertainty
Proceedings Papers

Analysis to Relate Data From Radial Compression Tests on Helical Springs to Tensile Material Properties

Andre Gagnon, Donald Metzger
Proc. ASME. PVP2022, Volume 2: Computer Technology and Bolted Joints; Design and Analysis, V002T02A025, July 17–22, 2022
Paper No: PVP2022-84892
DOI: https://doi.org/10.1115/PVP2022-84892
View Paper titled, Analysis to Relate Data From Radial Compression Tests on Helical Springs to Tensile Material Properties
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Topics: Compression, Materials properties, Springs, Stress, Geometry, Dimensions, Failure, Bending (Stress), Displacement, Errors
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
View Paper titled, Design Charts for an Integrated Creep-Fatigue Damage Evaluation Approach
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Topics: Creep, Damage, Design, Fatigue, High temperature, Alloys, Design methodology, Failure data, Fatigue damage, Nuclear reactors
Proceedings Papers

Advanced Structural Integrity Assessment Tools for Safe Long Term Operation (ATLAS+)

Sebastian Lindqvist, Anna Dahl, Mike Smith, Arnaud Blouin, Peter Dillström, Szabolcs Szavai, Tomas Nicak
Proc. ASME. PVP2022, Volume 4A: Materials and Fabrication, V04AT06A033, July 17–22, 2022
Paper No: PVP2022-80693
DOI: https://doi.org/10.1115/PVP2022-80693
View Paper titled, Advanced Structural Integrity Assessment Tools for Safe Long Term Operation (ATLAS+)
Click here to open pdf in another window PDF for Advanced Structural Integrity Assessment Tools for Safe Long Term Operation (ATLAS+)
Topics: Coolants, Fracture mechanics, Materials properties, Nuclear reactor coolants, Nuclear reactors, Piping systems, Pressure, Reactor vessels, Residual stresses, Safety
Proceedings Papers

ATLAS+ European Project - General Method for the Components J-R Curve Derivation

Tomas Nicak, Arnaud Blouin, Stephane Marie, Olivier Ancelet
Proc. ASME. PVP2022, Volume 4A: Materials and Fabrication, V04AT06A039, July 17–22, 2022
Paper No: PVP2022-84853
DOI: https://doi.org/10.1115/PVP2022-84853
View Paper titled, ATLAS+ European Project - General Method for the Components J-R Curve Derivation
Click here to open pdf in another window PDF for ATLAS+ European Project - General Method for the Components J-R Curve Derivation
Topics: Coolants, Fracture (Materials), Fracture mechanics, Geometry, Junctions, Materials properties, Nuclear reactors, Pipes, Pressure, Pressure vessels
Proceedings Papers

Advanced Structural Integrity Assessment Tools for Safe Long Term Operation - ATLAS+ Project: Status of the Activities of the WP3 on Modelling in 2020 & 2021

Arnaud Blouin, Stéphane Marie, Tomas Nicak, Antti Timperi, Peter Gill
Proc. ASME. PVP2022, Volume 4A: Materials and Fabrication, V04AT06A037, July 17–22, 2022
Paper No: PVP2022-84842
DOI: https://doi.org/10.1115/PVP2022-84842
View Paper titled, Advanced Structural Integrity Assessment Tools for Safe Long Term Operation - ATLAS+ Project: Status of the Activities of the WP3 on Modelling in 2020 & 2021
Click here to open pdf in another window PDF for Advanced Structural Integrity Assessment Tools for Safe Long Term Operation - ATLAS+ Project: Status of the Activities of the WP3 on Modelling in 2020 & 2021
Topics: Coolants, Fracture (Materials), Fracture toughness, Leak-before-break, Modeling, Nuclear reactors, Pipes, Pressure, Residual stresses
Proceedings Papers

Ductile Tearing Prediction of Ferritic Pipes by GTN Model for ATLAS+ European Project (Report 2)

Satoshi Kumagai, Kiminobu Hojo, Takatoshi Hirota, Keiji Kawanishi
Proc. ASME. PVP2022, Volume 4A: Materials and Fabrication, V04AT06A036, July 17–22, 2022
Paper No: PVP2022-84554
DOI: https://doi.org/10.1115/PVP2022-84554
View Paper titled, Ductile Tearing Prediction of Ferritic Pipes by GTN Model for ATLAS+ European Project (Report 2)
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Topics: Ductile fracture, Finite element analysis, Pipes, Fracture (Materials), Coolants, Damage mechanics, Errors, Fracture mechanics, Nuclear reactors, Pressure
Proceedings Papers

A Discussion of Strength Reduction Factor Development for Thermal Aging Effect on Nuclear Structural Alloys

Weiju Ren
Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A046, July 13–15, 2021
Paper No: PVP2021-61055
DOI: https://doi.org/10.1115/PVP2021-61055
View Paper titled, A Discussion of Strength Reduction Factor Development for Thermal Aging Effect on Nuclear Structural Alloys
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Topics: Alloys, Tensile strength, Design, Temperature, ASME Boiler and Pressure Vessel Code, Nuclear reactors, Safety, Service life (Equipment), Structural elements (Construction)
Proceedings Papers

Advanced Structural Integrity Assessment Tools for Safe Long Term Operation - ATLAS+ Project: Status of the Activities of the WP3 on Modelling in 2021

Arnaud Blouin, Stéphane Marie, Tomas Nicak, Antti Timperi, Peter Gill
Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A029, July 13–15, 2021
Paper No: PVP2021-62010
DOI: https://doi.org/10.1115/PVP2021-62010
View Paper titled, Advanced Structural Integrity Assessment Tools for Safe Long Term Operation - ATLAS+ Project: Status of the Activities of the WP3 on Modelling in 2021
Click here to open pdf in another window PDF for Advanced Structural Integrity Assessment Tools for Safe Long Term Operation - ATLAS+ Project: Status of the Activities of the WP3 on Modelling in 2021
Topics: Coolants, Fracture (Materials), Fracture toughness, Leak-before-break, Modeling, Nuclear reactors, Pipes, Pressure, Residual stresses
Proceedings Papers

An Update of the Assessment Methodology for Civil Ageing Management for LTO/CSO Based on International Standards and Engineering Judgement

F. H. E. de Haan - de Wilde, M. J. Janssen
Proc. ASME. PVP2021, Volume 5: Operations, Applications, and Components; Seismic Engineering; Non-Destructive Examination, V005T07A008, July 13–15, 2021
Paper No: PVP2021-61499
DOI: https://doi.org/10.1115/PVP2021-61499
View Paper titled, An Update of the Assessment Methodology for Civil Ageing Management for LTO/CSO Based on International Standards and Engineering Judgement
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Topics: Amperes, Concretes, Containment, Engineering standards, Finite element analysis, Maintenance, Modeling, Nuclear power stations, Nuclear reactors, Performance
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
View Paper titled, Simplified Criteria With Reduced Testing Effort for Selecting Clad Materials for High Temperature Reactor Structural Components
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Topics: High temperature, Structural elements (Construction), Testing, Creep, Design, Temperature, Alloys, Corrosion, Corrosion resistant materials, Design methodology
Proceedings Papers

Prediction of J-Integrals at Defects in W-9CR Steel Sandwich-Type Cooling Pipes

Tristan Calvet, Yiqiang Wang, Minh-Son Pham, Catrin M. Davies
Proc. ASME. PVP2021, Volume 2: Computer Technology and Bolted Joints; Design and Analysis, V002T03A064, July 13–15, 2021
Paper No: PVP2021-62878
DOI: https://doi.org/10.1115/PVP2021-62878
View Paper titled, Prediction of J-Integrals at Defects in W-9CR Steel Sandwich-Type Cooling Pipes
Click here to open pdf in another window PDF for Prediction of J-Integrals at Defects in W-9CR Steel Sandwich-Type Cooling Pipes
Topics: Brazing, Cooling, Heat flux, Pipes, Steel, Thermal stresses, Fracture (Materials), Manufacturing, Stress, Tungsten
Proceedings Papers

Research on Characteristics of Fluid Exciting Force of Reactor Internals

Zhipeng Feng, Liwen Deng, Xuan Huang, Pingchuan Shen, Shuai Liu, Fengchun Cai
Proc. ASME. PVP2021, Volume 3: Fluid Structure Interaction; High Pressure Technology, V003T04A005, July 13–15, 2021
Paper No: PVP2021-62128
DOI: https://doi.org/10.1115/PVP2021-62128
View Paper titled, Research on Characteristics of Fluid Exciting Force of Reactor Internals
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Topics: Flow-induced vibrations, Fluids, Reactor vessels, Pressure, Computational fluid dynamics, Design, Excitation, Flow (Dynamics), Large eddy simulation, Nuclear reactors
Proceedings Papers

The Creep Crack Growth Behavior of GH3535 Superalloy at 650°C

Fan Guangcheng, Wang Wanxia, Tan Jianping, Shi Kexian, Wang Songlin, Lu Yanling
Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A011, July 13–15, 2021
Paper No: PVP2021-61787
DOI: https://doi.org/10.1115/PVP2021-61787
View Paper titled, The Creep Crack Growth Behavior of GH3535 Superalloy at 650°C
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Topics: Creep, Fracture (Materials), Superalloys, Alloys, Stress, China, Grain boundaries, High temperature, Mechanical properties, Molten salt reactors
Proceedings Papers

Ductile Tearing Prediction of Ferritic Pipe Material by GTN Model for ATLAS+ European Project

Kiminobu Hojo, Takatoshi Hirota, Naoki Ogawa, Satoshi Kumagai
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A047, August 3, 2020
Paper No: PVP2020-21645
DOI: https://doi.org/10.1115/PVP2020-21645
View Paper titled, Ductile Tearing Prediction of Ferritic Pipe Material by GTN Model for ATLAS+ European Project
Click here to open pdf in another window PDF for Ductile Tearing Prediction of Ferritic Pipe Material by GTN Model for ATLAS+ European Project
Topics: Pipes, Fracture (Materials), Fracture (Process), Coolants, Ductile fracture, Fracture mechanics, Nuclear reactors, Pressure, Simulation, Stress
Proceedings Papers

Fabrication and Assembly of the First Accident Tolerant Fuel Concept for TREAT Testing

Connor Woolum, D. Devin Imholte, Austin Fleming, David Kamerman, Korbin Tritthart
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A078, August 3, 2020
Paper No: PVP2020-21620
DOI: https://doi.org/10.1115/PVP2020-21620
View Paper titled, Fabrication and Assembly of the First Accident Tolerant Fuel Concept for TREAT Testing
Click here to open pdf in another window PDF for Fabrication and Assembly of the First Accident Tolerant Fuel Concept for TREAT Testing
Topics: Accidents, Fuels, Irradiation (Radiation exposure), Manufacturing, Testing, Cladding systems (Building), Pressurized water reactors, Transients (Dynamics), Design, Fuel systems
Proceedings Papers

Fracture Toughness Tests on Western RPV Steels Using Small Scale Specimen Technique

Florian Obermeier, Eberhard Altstadt, Hieronymus Hein, Aniruddh Das
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A102, August 3, 2020
Paper No: PVP2020-21481
DOI: https://doi.org/10.1115/PVP2020-21481
View Paper titled, Fracture Toughness Tests on Western RPV Steels Using Small Scale Specimen Technique
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Topics: Embrittlement, Fracture mechanics, Fracture toughness, Irradiation (Radiation exposure), Reactor vessels, Steel, Surveillance, Displacement, Brittle fracture, Cracking (Materials)
Proceedings Papers

Study of the Influence of Microstructure and Intergranular Carbides on the Oxidation Behavior of a Nickel Base Alloy 690 TT in Supercritical Water Nuclear Reactor Conditions

Alberto Sáez-Maderuelo, María Luisa Ruiz-Lorenzo, Francisco Javier Perosanz, Patricie Halodová, Jan Prochazka, Hygreeva Namburi
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A077, August 3, 2020
Paper No: PVP2020-21518
DOI: https://doi.org/10.1115/PVP2020-21518
View Paper titled, Study of the Influence of Microstructure and Intergranular Carbides on the Oxidation Behavior of a Nickel Base Alloy 690 TT in Supercritical Water Nuclear Reactor Conditions
Click here to open pdf in another window PDF for Study of the Influence of Microstructure and Intergranular Carbides on the Oxidation Behavior of a Nickel Base Alloy 690 TT in Supercritical Water Nuclear Reactor Conditions
Topics: Alloys, Augers, Nickel, Nuclear reactors, Oxidation, Scanning electron microscopes, Water
Proceedings Papers

Assessment of the Continued Need for Independent Requirements on Transition Temperature and Upper Shelf Charpy Impact Toughness Metrics in Regulations Pertaining to Nuclear Reactor Pressure Vessels

Mark Kirk, Masato Yamamoto, Marjorie Erickson
Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A057, August 3, 2020
Paper No: PVP2020-21186
DOI: https://doi.org/10.1115/PVP2020-21186
View Paper titled, Assessment of the Continued Need for Independent Requirements on Transition Temperature and Upper Shelf Charpy Impact Toughness Metrics in Regulations Pertaining to Nuclear Reactor Pressure Vessels
Click here to open pdf in another window PDF for Assessment of the Continued Need for Independent Requirements on Transition Temperature and Upper Shelf Charpy Impact Toughness Metrics in Regulations Pertaining to Nuclear Reactor Pressure Vessels
Topics: Fracture toughness, Nuclear reactors, Phase transition temperature, Pressure vessels, Regulations, Steel, Nuclear power stations, Pressure
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
View Paper titled, Development of Design Method for High Temperature Nuclear Reactor Cladded Components
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Topics: Design methodology, High temperature, Nuclear reactors, Design, Coolants, Corrosion resistant materials, Corrosion, Creep, Failure, Finite element analysis