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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

Exploring Life Extension Opportunities of High-Pressure Hydrogen Pressure Vessels at Refueling Stations

Joseph A. Ronevich, Chris San Marchi, Dusty Brooks, John M. Emery, Peter Grimmer, Eileen Chant, J. Robert Sims, Alex Belokobylka, Dave Farese, John Felbaum

Proc. ASME. PVP2021, Volume 3: Fluid Structure Interaction; High Pressure Technology, V003T05A011, July 13–15, 2021

Paper No: PVP2021-61815

DOI: https://doi.org/10.1115/PVP2021-61815

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Topics: High pressure (Physics), Hydrogen, Life extension, Pressure vessels, Design, Cycles, Pressure, Vessels, Fatigue life, Fracture (Materials)

Proceedings Papers

Design and Test of Pressure Vessels for Contained Blast and Fragment Impact

Greg Wattis, James Mathis, Laura Hunt, Scott Mullin, Steven Beissel

Proc. ASME. PVP2021, Volume 3: Fluid Structure Interaction; High Pressure Technology, V003T05A016, July 13–15, 2021

Paper No: PVP2021-62086

DOI: https://doi.org/10.1115/PVP2021-62086

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Topics: Design, Finite element analysis, Pressure, Pressure vessels, Testing, Vessels, Construction, Steel, ASME Boiler and Pressure Vessel Code, Cycles

Proceedings Papers

Designing and Optimising Duplex/Superduplex Compact Flanges to Negate HISC in Subsea Applications

Przemyslaw Lutkiewicz

Proc. ASME. PVP2021, Volume 3: Fluid Structure Interaction; High Pressure Technology, V003T05A003, July 13–15, 2021

Paper No: PVP2021-61347

DOI: https://doi.org/10.1115/PVP2021-61347

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Topics: Design, Flanges, Genetic algorithms, Ocean engineering, Optimization

Proceedings Papers

Limit Loads of Bolted Flange Connections

Finn Kirkemo, Przemyslaw Lutkiewicz

Proc. ASME. PVP2021, Volume 3: Fluid Structure Interaction; High Pressure Technology, V003T05A004, July 13–15, 2021

Paper No: PVP2021-62712

DOI: https://doi.org/10.1115/PVP2021-62712

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Topics: Bolted flanges, Design, Stress

Proceedings Papers

Pilot Study on Seismic Fragility Evaluation for Degraded Austenitic Stainless Steel Piping Using the Probabilistic Fracture Mechanics Code PASCAL-SP

Kisaburo Azuma, Yoshihito Yamaguchi, Yinsheng Li

Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A063, July 13–15, 2021

Paper No: PVP2021-62233

DOI: https://doi.org/10.1115/PVP2021-62233

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Topics: Fracture mechanics, Pipes, Stainless steel, Inspection, Maintenance, Stress corrosion cracking, Failure, Probabilistic risk assessment, Probability, Design

Proceedings Papers

Assessment of Flaws in Non-Stress Relieved Carbon Steel Welds Caused by Hydrogen Attack

K. E. Bagnoli, Z. A. Cater-Cyker, C. A. Hay, R. L. Holloman, Y. Hioe, G. Wilkowski, B. C. Rollins, K. M. Nikbin

Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A033, July 13–15, 2021

Paper No: PVP2021-61603

DOI: https://doi.org/10.1115/PVP2021-61603

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Topics: Carbon steel, Hydrogen, Stress, Welded joints, Fracture (Materials), Damage, Steel, Creep, High temperature, Inspection

Proceedings Papers

Development of Mini-Compact Tension Specimen Fabrication and Test Methods in Hot Cell for Post-Irradiation Examination of Reactor Pressure Vessel Steels

Frideriki Naziris, Casper Versteylen, Frederick Frith, Marcel Bregman, Murthy Kolluri

Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A064, July 13–15, 2021

Paper No: PVP2021-61027

DOI: https://doi.org/10.1115/PVP2021-61027

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Topics: Irradiation (Radiation exposure), Manufacturing, Reactor vessels, Steel, Tension, Testing, Geometry, Stress, ASTM International, Pressurized water reactors

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

European Project ATLAS+: Large Scale Fracture Mechanics Tests on Ferritic Pipes

Anna Dahl, Willy Vincent

Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A028, July 13–15, 2021

Paper No: PVP2021-61834

DOI: https://doi.org/10.1115/PVP2021-61834

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Topics: Fracture mechanics, Pipes, Steel, Fracture (Materials), Design, Feedwater, Pressurized water reactors, Shapes, Stainless steel, Temperature

Proceedings Papers

Full-Scale Hydrostatic Test of Internal CFRP Repair on a Degraded Pipe With a Postulated Flaw for Short-Term Loading in Safety Related Nuclear Applications

M. Uddin, F. Orth, Y. Hioe, P. Krishnaswamy, L. Smith, C. Basavaraju

Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A022, July 13–15, 2021

Paper No: PVP2021-63062

DOI: https://doi.org/10.1115/PVP2021-63062

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Topics: Carbon reinforced plastics, Hydrostatic testing, Maintenance, Pipes, Safety, Design, Boilers, Failure, Failure mechanisms, Glass fibers

Proceedings Papers

Secondary Stress Weighting Factor and Plastic Reduction Factor for Circumferential Surface Cracked Pipe and Elbow Tests at Elevated Temperature and Internal Pressure

S. Pothana, G. Wilkowski, S. Kalyanam, Y. Hioe, F. Brust, F. Orth, P. Krishnaswamy, G. Hattery, S. Burger, S. Gilbert

Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A045, July 13–15, 2021

Paper No: PVP2021-60449

DOI: https://doi.org/10.1115/PVP2021-60449

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Topics: Pipes, Pressure, Stress, Temperature, Fracture (Materials), Rotation, Displacement, Design, Fracture toughness, Pipe sizes

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

Investigation of the Internal Impact During a 9 M Drop Test of an Accident-Safe Waste Package

Marko Nehrig, Robert Scheidemann, Frank Wille, Viktor Ballheimer

Proc. ASME. PVP2021, Volume 5: Operations, Applications, and Components; Seismic Engineering; Non-Destructive Examination, V005T07A023, July 13–15, 2021

Paper No: PVP2021-60996

DOI: https://doi.org/10.1115/PVP2021-60996

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Topics: Accidents, Regulations, Safety, Containment systems, Design, Heat conduction, Leakage, Radioactive substances, Stress, Temperature

Proceedings Papers

Transient Thermal Modeling of the High Burnup Demonstration Research Project Cask Using STAR-CCM+ and COBRA-SFS

D. J. Richmond, J. A. Fort, S. R. Suffield

Proc. ASME. PVP2021, Volume 5: Operations, Applications, and Components; Seismic Engineering; Non-Destructive Examination, V005T07A031, July 13–15, 2021

Paper No: PVP2021-62082

DOI: https://doi.org/10.1115/PVP2021-62082

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Topics: Computational fluid dynamics, Design, Modeling, Temperature, Transients (Dynamics), Drying, Steady state, Fuels, Spent nuclear fuels, Storage

Proceedings Papers

Study on Reliability of Seismic Capacity Analysis for Important Equipment in Nuclear Facilities

Hitoshi Muta, Yasuki Ohtori, Osamu Furuya, Satoshi Fujita

Proc. ASME. PVP2021, Volume 5: Operations, Applications, and Components; Seismic Engineering; Non-Destructive Examination, V005T08A021, July 13–15, 2021

Paper No: PVP2021-61742

DOI: https://doi.org/10.1115/PVP2021-61742

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Topics: Nuclear power stations, Reliability, Safety, Accidents, Design, Countermeasures, Fukushima nuclear disaster, Japan, 2011, Regulations, Defense industry, Earthquake risk

Proceedings Papers

Spent Nuclear Fuel Mechanical Loads in the General Package Drop Scenario

Nicholas Klymyshyn, Casey Spitz, Pavlo Ivanusa, Kevin Kadooka, James Fitzpatrick

Proc. ASME. PVP2021, Volume 5: Operations, Applications, and Components; Seismic Engineering; Non-Destructive Examination, V005T07A026, July 13–15, 2021

Paper No: PVP2021-61617

DOI: https://doi.org/10.1115/PVP2021-61617

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Topics: Spent nuclear fuels, Stress, Damage, Manufacturing, Boundary element methods, Design, Dynamic analysis, Finite element analysis, Finite element model, Fuels

Proceedings Papers

Structural Dynamics Modeling of Spent Nuclear Fuel During Hypothetical Package Drop Events

Kevin Kadooka, James Fitzpatrick, Nicholas Klymyshyn

Proc. ASME. PVP2021, Volume 5: Operations, Applications, and Components; Seismic Engineering; Non-Destructive Examination, V005T07A025, July 13–15, 2021

Paper No: PVP2021-61610

DOI: https://doi.org/10.1115/PVP2021-61610

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Topics: Modeling, Spent nuclear fuels, Structural dynamics, Fuels, Shock (Mechanics), Transportation systems, Boundary element methods, Buckling, Cladding systems (Building), Design

Proceedings Papers

Experimental Investigation on the Seismic Performance of a Multi-Component System for Major-Hazard Industrial Facilities

Christoph Butenweg, Oreste S. Bursi, Chiara Nardin, Igor Lanese, Alberto Pavese, Marko Marinković, Fabrizio Paolacci, Gianluca Quinci

Proc. ASME. PVP2021, Volume 5: Operations, Applications, and Components; Seismic Engineering; Non-Destructive Examination, V005T08A016, July 13–15, 2021

Paper No: PVP2021-61696

DOI: https://doi.org/10.1115/PVP2021-61696

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Topics: Damage, Design, Earthquake engineering, Earthquake resistant design, Earthquakes, Hazardous substances, Hazards, Industrial plants, Pipes, Risk

Proceedings Papers

A Viscoplastic Model for Alloy 617 for Use With the ASME Section III, Division 5 Design by Inelastic Analysis Rules

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

Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A034, July 13–15, 2021

Paper No: PVP2021-61607

DOI: https://doi.org/10.1115/PVP2021-61607

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Topics: Alloys, Design, Inelastic analysis, Creep, Deformation, Fatigue, ASME Boiler and Pressure Vessel Code, Computer software, Databases, Elastic analysis

2 3 4 5

NARROW

Research on Characteristics of Fluid Exciting Force of Reactor Internals

Exploring Life Extension Opportunities of High-Pressure Hydrogen Pressure Vessels at Refueling Stations

Design and Test of Pressure Vessels for Contained Blast and Fragment Impact

Designing and Optimising Duplex/Superduplex Compact Flanges to Negate HISC in Subsea Applications

Limit Loads of Bolted Flange Connections

Pilot Study on Seismic Fragility Evaluation for Degraded Austenitic Stainless Steel Piping Using the Probabilistic Fracture Mechanics Code PASCAL-SP

Assessment of Flaws in Non-Stress Relieved Carbon Steel Welds Caused by Hydrogen Attack

Development of Mini-Compact Tension Specimen Fabrication and Test Methods in Hot Cell for Post-Irradiation Examination of Reactor Pressure Vessel Steels

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

European Project ATLAS+: Large Scale Fracture Mechanics Tests on Ferritic Pipes

Full-Scale Hydrostatic Test of Internal CFRP Repair on a Degraded Pipe With a Postulated Flaw for Short-Term Loading in Safety Related Nuclear Applications

Secondary Stress Weighting Factor and Plastic Reduction Factor for Circumferential Surface Cracked Pipe and Elbow Tests at Elevated Temperature and Internal Pressure

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

Investigation of the Internal Impact During a 9 M Drop Test of an Accident-Safe Waste Package

Transient Thermal Modeling of the High Burnup Demonstration Research Project Cask Using STAR-CCM+ and COBRA-SFS

Study on Reliability of Seismic Capacity Analysis for Important Equipment in Nuclear Facilities

Spent Nuclear Fuel Mechanical Loads in the General Package Drop Scenario

Structural Dynamics Modeling of Spent Nuclear Fuel During Hypothetical Package Drop Events

Experimental Investigation on the Seismic Performance of a Multi-Component System for Major-Hazard Industrial Facilities

A Viscoplastic Model for Alloy 617 for Use With the ASME Section III, Division 5 Design by Inelastic Analysis Rules

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