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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
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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
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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
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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
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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
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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
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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
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Topics: Ductile fracture, Finite element analysis, Pipes, Fracture (Materials), Coolants, Damage mechanics, Errors, Fracture mechanics, Nuclear reactors, Pressure
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

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
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Topics: Brazing, Cooling, Heat flux, Pipes, Steel, Thermal stresses, Fracture (Materials), Manufacturing, Stress, Tungsten
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
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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
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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
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Topics: Amperes, Concretes, Containment, Engineering standards, Finite element analysis, Maintenance, Modeling, Nuclear power stations, Nuclear reactors, Performance
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
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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
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Topics: Creep, Fracture (Materials), Superalloys, Alloys, Stress, China, Grain boundaries, High temperature, Mechanical properties, Molten salt reactors
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
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Topics: Alloys, Augers, Nickel, Nuclear reactors, Oxidation, Scanning electron microscopes, Water
Proceedings Papers

Recent Argonne National Laboratory Estimated Thermal Expansion Coefficients for Reactor Pressure Boundary Base Metal, Similar and Dissimilar Metal Welds

Subhasish Mohanty, Joseph Listwan
Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A024, August 3, 2020
Paper No: PVP2020-21828
DOI: https://doi.org/10.1115/PVP2020-21828
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Topics: Base metals, Metals, Pressure, Thermal expansion, Welded joints, Fillers (Materials), Nuclear reactors, Safety, Stress, Stress analysis (Engineering)
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

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