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Proceedings Papers

State of the Art in CUF-Based Fatigue Assessment & Related Issues From Regulatory and Code Perspectives for Long-Term Operation

Yogendra Garud

Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A019, July 17–22, 2022

Paper No: PVP2022-86189

DOI: https://doi.org/10.1115/PVP2022-86189

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Topics: Fatigue, Design, Regulations, Stress, Cycles, Engineering standards, Engineering systems and industry applications, Failure, Fracture (Materials), Metal fatigue

Proceedings Papers

Criteria for Specifying Static Equipment Construction Code for Process Plant

Kamlesh Chikhaliya, Ruediger Gawlick

Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A081, July 17–22, 2022

Paper No: PVP2022-78987

DOI: https://doi.org/10.1115/PVP2022-78987

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Topics: Construction, Design, Temperature, Corrosion, Heat exchangers, Pressure vessels, Regulations, Safety, Weight (Mass)

Proceedings Papers

Design Modification Implementations for Mitigating the Reactor Inner Zone Inlet Header Temperature in CANDU Reactor Units

Preston Tang, Bing Li, Akash Bhatia, Leon Cramer

Proc. ASME. PVP2022, Volume 2: Computer Technology and Bolted Joints; Design and Analysis, V002T03A024, July 17–22, 2022

Paper No: PVP2022-85985

DOI: https://doi.org/10.1115/PVP2022-85985

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Topics: Design, Temperature, Boilers, Feedwater, Heat, High pressure (Physics), Magnetite, Pipes, Regulations, Safety

Proceedings Papers

Large-Scale Parametric Modeling of Spent Nuclear Fuel Dynamics in the 30 cm Package Drop Scenario

Kevin Kadooka, James Fitzpatrick, Nicholas Klymyshyn

Proc. ASME. PVP2022, Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division, V005T07A030, July 17–22, 2022

Paper No: PVP2022-84747

DOI: https://doi.org/10.1115/PVP2022-84747

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Topics: Dynamics (Mechanics), Modeling, Spent nuclear fuels, Fuels, Manufacturing, Simulation, Stress, Boiling water reactors, Cladding systems (Building), Fuel rods

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

30 CM Horizontal Drop of a Surrogate 17x17 PWR Fuel Assembly

Elena Kalinina, Doug Ammerman, Carissa Grey, Gregg Flores, Lucas Lujan, Sylvia Saltzstein, Danielle Michel

Proc. ASME. PVP2021, Volume 5: Operations, Applications, and Components; Seismic Engineering; Non-Destructive Examination, V005T07A022, July 13–15, 2021

Paper No: PVP2021-60533

DOI: https://doi.org/10.1115/PVP2021-60533

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Topics: Cladding systems (Building), Fuels, Manufacturing, Pressure, Pressurized water reactors, Spent nuclear fuels, Stress-strain curves, Arches, Bending (Stress), Blanks

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

Comparative Assessments of Different Leakage-Rate Models for ATLAS+

P. T. Williams, B. R. Bass, P. Dillström, P. Gill, B. Daniels, R. Lammert, G. Wackenhut

Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A030, July 13–15, 2021

Paper No: PVP2021-62046

DOI: https://doi.org/10.1115/PVP2021-62046

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Topics: Leakage, Pipes, Statistical distributions, Uncertainty, Failure, Fitness-for-service, Leak-before-break, Probability, Regulations, Rupture

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

Research on Regulations and Standards for Inspection of Atmospheric Liquid Metal Tank Trucks for Hazardous Chemicals

Zhou Fang, Zhe Wang, Guanghai Li

Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A076, August 3, 2020

Paper No: PVP2020-21067

DOI: https://doi.org/10.1115/PVP2020-21067

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Topics: Inspection, Liquid metals, Regulations, Road transport, Trucks

Proceedings Papers

Outcomes of Three Large Scale Fire Reference Tests Conducted in BAM Fire Test Facility

Martin Feldkamp, Thomas Quercetti, Frank Wille

Proc. ASME. PVP2020, Volume 8: Operations, Applications, and Components, V008T08A038, August 3, 2020

Paper No: PVP2020-21245

DOI: https://doi.org/10.1115/PVP2020-21245

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Topics: Fire, Fire testing, Performance, Temperature, Heat, Accidents, Flux (Metallurgy), Flames, Radioactive substances, Steel sheet

Proceedings Papers

Structural Analysis Approach for the Defense Programs Package 3 (DPP-3)

Peter J. Sakalaukus, Jr., Nathan P. Barrett, Brian J. Koeppel

Proc. ASME. PVP2020, Volume 8: Operations, Applications, and Components, V008T08A039, August 3, 2020

Paper No: PVP2020-21259

DOI: https://doi.org/10.1115/PVP2020-21259

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Topics: ASME Boiler and Pressure Vessel Code, Defense industry, Finite element analysis, Structural analysis, Testing, Design, Computer software, Containment vessels, Damage, Hazardous substances

Proceedings Papers

New French Nuclear Pressure Equipment Regulation in 2019 and Use of Codes

Philippe Malouines, Andrew Wasylyk, Pascal Duranton

Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A080, July 14–19, 2019

Paper No: PVP2019-93033

DOI: https://doi.org/10.1115/PVP2019-93033

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Topics: Pressure equipment, Regulations, Safety, Design, Manufacturing, Pressure Equipment Directive, Public utilities, Risk, Risk analysis

Proceedings Papers

Comparative Risks of Hydrostatic and Pneumatic Pipeline Testing

David A. Simpson

Proc. ASME. PVP2019, Volume 7: Operations, Applications, and Components, V007T07A003, July 14–19, 2019

Paper No: PVP2019-93048

DOI: https://doi.org/10.1115/PVP2019-93048

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Topics: Hydrostatics, Pipelines, Testing, Fluids, Risk, Preferences, Pipes, Hydrostatic testing, Internal energy (Physics), Pressure

Proceedings Papers

Estimation of Impact Energy for Seat Seals in Spring-Operated Pressure Relief Valves During the Reseating Process Under Compressible Fluid Service Conditions

Alex Schimanowski, Josef Schlattmann

Proc. ASME. PVP2019, Volume 3: Design and Analysis, V003T03A030, July 14–19, 2019

Paper No: PVP2019-93336

DOI: https://doi.org/10.1115/PVP2019-93336

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Topics: Fluids, Relief valves, Springs, Disks, Valves, Regulations, American Petroleum Institute, Containment, Cycles, Reliability

Proceedings Papers

RCC-M Code: Main Evolutions From the 2016 to 2018 Editions

Manuela Triay, Benoit Lefever, Julien Quéré, Jean-Luc Gobert, Emmanuel Chantelat, Sylvain Puybouffat, Julien Cadith, Eric Meister

Proc. ASME. PVP2018, Volume 1B: Codes and Standards, V01BT01A051, July 15–20, 2018

Paper No: PVP2018-84409

DOI: https://doi.org/10.1115/PVP2018-84409

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Topics: Construction, Design, Engineering standards, In-service inspection, Regulations

Proceedings Papers

Comparisons of Testing Methods for High-Pressure Hydrogen Storage Container Under the Law and Regulation System of UN and EU

Bo Yang, Jian-ping Yao, Yi-wen Yuan, Jie-lu Wang, Yao-zhou Qian, Xiao-ying Tang

Proc. ASME. PVP2018, Volume 1B: Codes and Standards, V01BT01A044, July 15–20, 2018

Paper No: PVP2018-84808

DOI: https://doi.org/10.1115/PVP2018-84808

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Topics: Containers, High pressure (Physics), Hydrogen storage, Testing, Hydrogen fuels, Regulations, Fuels, Gasoline, Hydrogen, Mass production

Proceedings Papers

Study on Promoting Use of Repair, Replacement and Mitigation Techniques in Maintenance Activities of Nuclear Power Plants

Koji Dozaki, Takayuki Aoki, Koji Koyama, Masanori Kanno, Ryoichi Saeki

Proc. ASME. PVP2018, Volume 1B: Codes and Standards, V01BT01A062, July 15–20, 2018

Paper No: PVP2018-84512

DOI: https://doi.org/10.1115/PVP2018-84512

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Topics: Maintenance, Nuclear power stations, Inspection, Hardware, Countermeasures, Nuclear power, Plant construction, Public utilities, Regulations, Risk

Proceedings Papers

Benchmark of Finite Elements and Extended-Finite Elements Methods for Stress Intensity Factors and Crack Propagation

Rémi Lacroix, Axelle Caron, Sandrine Dischert, Hubert Deschanels, Moïse Pignol

Proc. ASME. PVP2018, Volume 3B: Design and Analysis, V03BT03A026, July 15–20, 2018

Paper No: PVP2018-84401

DOI: https://doi.org/10.1115/PVP2018-84401

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Topics: Crack propagation, Finite element analysis, Stress, Fracture (Materials), Finite element methods, Nuclear power stations, Computer software, Fatigue cracks, Geometry, Regulations

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NARROW

State of the Art in CUF-Based Fatigue Assessment & Related Issues From Regulatory and Code Perspectives for Long-Term Operation

Criteria for Specifying Static Equipment Construction Code for Process Plant

Design Modification Implementations for Mitigating the Reactor Inner Zone Inlet Header Temperature in CANDU Reactor Units

Large-Scale Parametric Modeling of Spent Nuclear Fuel Dynamics in the 30 cm Package Drop Scenario

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

30 CM Horizontal Drop of a Surrogate 17x17 PWR Fuel Assembly

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

Comparative Assessments of Different Leakage-Rate Models for ATLAS+

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

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

Research on Regulations and Standards for Inspection of Atmospheric Liquid Metal Tank Trucks for Hazardous Chemicals

Outcomes of Three Large Scale Fire Reference Tests Conducted in BAM Fire Test Facility

Structural Analysis Approach for the Defense Programs Package 3 (DPP-3)

New French Nuclear Pressure Equipment Regulation in 2019 and Use of Codes

Comparative Risks of Hydrostatic and Pneumatic Pipeline Testing

Estimation of Impact Energy for Seat Seals in Spring-Operated Pressure Relief Valves During the Reseating Process Under Compressible Fluid Service Conditions

RCC-M Code: Main Evolutions From the 2016 to 2018 Editions

Comparisons of Testing Methods for High-Pressure Hydrogen Storage Container Under the Law and Regulation System of UN and EU

Study on Promoting Use of Repair, Replacement and Mitigation Techniques in Maintenance Activities of Nuclear Power Plants

Benchmark of Finite Elements and Extended-Finite Elements Methods for Stress Intensity Factors and Crack Propagation

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