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Proceedings Papers

Using Radius of Gyration in Order to Determine Surrogate Mechanical Properties of a Porous Structure

Oksana V. Shiman, Michel Gaudet
Proc. ASME. ICONE31, Volume 9: Advanced Methods of Manufacturing for Nuclear Reactors and Components; Severe Accidents and Mitigation Strategies for Beyond Design Basis Events, V009T10A003, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-133321
https://doi.org/10.1115/ICONE31-133321
View Paper titled, Using Radius of Gyration in Order to Determine Surrogate Mechanical Properties of a Porous Structure
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Topics: Additive manufacturing, Finite element analysis, Mechanical properties, Bulk solids, Design, Materials properties, Poisson ratio, Printing, Young's modulus
Proceedings Papers

Pure Lead Thermodynamic Properties in SIMMER-III Code: A Comparative Review and New Evaluation Proposal

Alessandro Bellomo, Mattia Massone, Simone Gianfelici, Koji Morita, Mariano Tarantino, Alessio Pesetti, Vittorio Cossu, Andrei Rineiski
Proc. ASME. ICONE31, Volume 10: Risk Assessments and Management; Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V010T13A016, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136243
https://doi.org/10.1115/ICONE31-136243
View Paper titled, Pure Lead Thermodynamic Properties in SIMMER-III Code: A Comparative Review and New Evaluation Proposal
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Topics: Equations of state, Fast neutron reactors, Thermodynamic properties, Heat capacity, Accidents, Design, Liquid metals, Pressure, Sodium fast reactors, Boilers
Proceedings Papers

Comparative Study on Creep-Fatigue Damage Assessment Between R5 Procedures and a Full Inelastic Analysis

Antony M. Hurst, Louis C. W. Chang, Nak-Kyun Cho
Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A008, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91707
https://doi.org/10.1115/ICONE29-91707
View Paper titled, Comparative Study on Creep-Fatigue Damage Assessment Between R5 Procedures and a Full Inelastic Analysis
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Topics: Creep, Damage assessment, Fatigue, Inelastic analysis, Stress, Damage, Elastic analysis, Cracking (Materials), Fracture (Process), Geometry
Proceedings Papers

Study on Dehumidification of Carbon Materials Based on Thermogravimetry

Da Yan, Kaiyue Shen, Yicheng Guo, Huaqiang Yin, Xuedong He, Tao Ma
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T02A004, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-63633
https://doi.org/10.1115/ICONE28-63633
View Paper titled, Study on Dehumidification of Carbon Materials Based on Thermogravimetry
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Topics: Carbon, Dehumidification, Thermogravimetry, Very high temperature reactors, Temperature, Boron, Graphite, High temperature, Corrosion, Desorption
Proceedings Papers

Sensitivity Study on TRISO Fuel Failure Probability Evaluation for HTGR

Jian Li, Ding She, Lei Shi
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A008, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64154
https://doi.org/10.1115/ICONE28-64154
View Paper titled, Sensitivity Study on TRISO Fuel Failure Probability Evaluation for HTGR
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Topics: Failure, Fuels, Probability, Very high temperature reactors, Irradiation (Radiation exposure), Particulate matter, Stress, Materials properties, Temperature, Anisotropy
Proceedings Papers

Study of the Ageing Effects on the Lower Head Failure in a PWR Reactor

R. Lo Frano, S. Paci, P. Darnowski, P. Mazgaj
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T01A016, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16664
https://doi.org/10.1115/ICONE2020-16664
View Paper titled, Study of the Ageing Effects on the Lower Head Failure in a PWR Reactor
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Topics: Failure, Finite element methods, Pressurized water reactors, Accidents, Nuclear power stations, Reactor vessels, Boundary-value problems, Computers, Engineering simulation, Materials properties
Proceedings Papers

Probability of Rupture for WWER-1000 Main Piping

Yaroslav Dubyk, Maksym Zarazovskii, Sergii Ageiev, Vladislav Filonov
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T10A014, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16897
https://doi.org/10.1115/ICONE2020-16897
View Paper titled, Probability of Rupture for WWER-1000 Main Piping
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Topics: Leakage, Pipes, Probability, Rupture, Stress, Fracture (Materials), Accounting, Flow (Dynamics), Fracture toughness, Nuclear power stations
Proceedings Papers

First Steps Towards the Development of a 3D Nuclear Fuel Behavior Solver With OpenFOAM

Alessandro Scolaro, Ivor Clifford, Carlo Fiorina, Andreas Pautz
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A051, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82381
https://doi.org/10.1115/ICONE26-82381
View Paper titled, First Steps Towards the Development of a 3D Nuclear Fuel Behavior Solver With OpenFOAM
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Topics: Nuclear fuels, Temperature, Electrical conductance, Fuels, Materials properties, Cracking (Materials), Creep, Databases, Fracture (Process), Fuel rods
Proceedings Papers

Nonlinear Analysis in Pressure Vessel Design Codes: Recommendations for Codified Rules Improvements

Claude Faidy
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A001, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81095
https://doi.org/10.1115/ICONE26-81095
View Paper titled, Nonlinear Analysis in Pressure Vessel Design Codes: Recommendations for Codified Rules Improvements
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Topics: Design, Pressure vessels, Stress, Failure mechanisms, Materials properties, Stress analysis (Engineering), Collapse, Constitutive equations, Failure, Fatigue
Proceedings Papers

A Systematic Study of the Material Performance of Hot Isostatically Pressed Type 316L Stainless Steel Powder for the Civil Nuclear Sector

William Kyffin, David Gandy, Barry Burdett
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A017, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81438
https://doi.org/10.1115/ICONE26-81438
View Paper titled, A Systematic Study of the Material Performance of Hot Isostatically Pressed Type 316L Stainless Steel Powder for the Civil Nuclear Sector
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Topics: Stainless steel, Manufacturing, Materials properties, Oxygen, ASTM International, Collaboration, Cycles, Defense industry, Electricity (Physics), Hot pressing
Proceedings Papers

Virtual Prototyping and Simulation of Robotic Devices and Maintenance Procedures for Remote Handling Activities in the Access Cell of DONES

Stefano Papa, Giuseppe di Gironimo, Federica Casoria, Gioacchino Micciché
Proc. ASME. ICONE26, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs, V001T01A016, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82390
https://doi.org/10.1115/ICONE26-82390
View Paper titled, Virtual Prototyping and Simulation of Robotic Devices and Maintenance Procedures for Remote Handling Activities in the Access Cell of DONES
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Topics: Maintenance, Robotics, Simulation, Kinematics, Chain, Collaboration, Conceptual design, Cranes, Degrees of freedom, End effectors
Proceedings Papers

New Needs of Fracture Mechanic Analysis at Design and Operation Level: Status of French Nuclear Mechanical Codes

Claude Faidy
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A002, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81096
https://doi.org/10.1115/ICONE26-81096
View Paper titled, New Needs of Fracture Mechanic Analysis at Design and Operation Level: Status of French Nuclear Mechanical Codes
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Topics: Design, Fracture (Materials), Fracture (Process), Boilers, Brittle fracture, Brittleness, Failure, In-service inspection, Leak-before-break, Manufacturing
Proceedings Papers

Adjoint Sensitivity Analysis of a Cooling Tower

Federico Di Rocco, Dan Gabriel Cacuci
Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A057, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67744
https://doi.org/10.1115/ICONE25-67744
View Paper titled, Adjoint Sensitivity Analysis of a Cooling Tower
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Topics: Cooling towers, Sensitivity analysis, Heat, Boundary-value problems, Computation, Computer simulation, Energy generation, Materials properties, Modeling, Nonlinear systems
Proceedings Papers

Structural Integrity Assessment to Justify Increase in Upper Operating Temperature Limit of AGR Dome

Antony M. Hurst
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A067, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66859
https://doi.org/10.1115/ICONE25-66859
View Paper titled, Structural Integrity Assessment to Justify Increase in Upper Operating Temperature Limit of AGR Dome
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Topics: Domes (Structural elements), Operating temperature, Temperature, Failure, Creep, Safety, Welded joints, Diaphragms (Mechanical devices), Diaphragms (Structural), Failure mechanisms
Proceedings Papers

An Image-Based Micro-Scale Fracture Model for Weld Zone in Nuclear Pipe and Component

Xiaoming Bai, Liangang Zheng, Xinjun Wang, Xi Lv
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A047, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66441
https://doi.org/10.1115/ICONE25-66441
View Paper titled, An Image-Based Micro-Scale Fracture Model for Weld Zone in Nuclear Pipe and Component
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Topics: Fracture (Materials), Fracture (Process), Microscale devices, Pipes, Finite element analysis, Boundary-value problems, Damping, Engineering standards, Materials properties, Mechanical properties
Proceedings Papers

The Applicability Study on the Multi-Layer Shell Element Method in Steel Concrete Structure of Shield Building

Wei Chao
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A106, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67677
https://doi.org/10.1115/ICONE25-67677
View Paper titled, The Applicability Study on the Multi-Layer Shell Element Method in Steel Concrete Structure of Shield Building
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Topics: Concretes, Shells, Steel, Finite element analysis, Aircraft, Composite materials, Computer software, Design, Emission spectroscopy, Exterior walls
Proceedings Papers

Innovative Methodology of Ranking Cooling Towers Based on Structural Safety Margin

Nhu-Cuong Tran, Charles Toulemonde, François Beaudouin, Christian Meuwisse, Nicolas Schmitt, Abderrazzaq El-Yazidi, Alexis Courtois, Yves Genest, Sylvain Moriceau
Proc. ASME. ICONE25, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle and Balance of Plant; I&C, Digital Controls, and Influence of Human Factors, V001T01A042, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67596
https://doi.org/10.1115/ICONE25-67596
View Paper titled, Innovative Methodology of Ranking Cooling Towers Based on Structural Safety Margin
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Topics: Cooling towers, Safety, Risk, Shells, Columns (Structural), Failure, Maintenance, Corrosion, Damage, Deformation
Proceedings Papers

Design of SC Walls and Connections in Nuclear Facilities

Amit H. Varma, Saahastaranshu R. Bhardwaj, Sanjeev R. Malushte
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T03A029, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60962
https://doi.org/10.1115/ICONE24-60962
View Paper titled, Design of SC Walls and Connections in Nuclear Facilities
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Topics: Design, Nuclear power stations, Steel, Failure, Quality control, Shear (Mechanics), Stress, Wall panels, Accidents, Buckling
Proceedings Papers

Qualification of Water-Filled Tank due to Tornado Missile Impact

Timothy A. Schmitt, Taha Al-Shawaf, Syed M. Rahman, Angelo Cristobal
Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T13A006, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60225
https://doi.org/10.1115/ICONE24-60225
View Paper titled, Qualification of Water-Filled Tank due to Tornado Missile Impact
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Topics: Missiles, Water, Fukushima nuclear disaster, Japan, 2011, Accidents, Materials properties, Stress, Computer software, Design, Diluents, Failure
Proceedings Papers

Implementation of Small Punch Testing and Automated Ball Indentation in the Process of Irradiated NPP Materials Degradation Evaluation

Radim Kopriva, Ivana Eliasova, Milos Kytka
Proc. ASME. ICONE24, Volume 5: Student Paper Competition, V005T15A043, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60620
https://doi.org/10.1115/ICONE24-60620
View Paper titled, Implementation of Small Punch Testing and Automated Ball Indentation in the Process of Irradiated NPP Materials Degradation Evaluation
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Topics: Materials degradation, Nuclear power stations, Testing, Surveillance, Materials properties, Materials testing, Mechanical testing, Testing equipment, Databases, Design