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Proceedings Papers

Comparison of International Codes for a Fatigue Crack Growth Flaw Tolerance Sample Problem

Gary L. Stevens
Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A008, July 13–15, 2021
Paper No: PVP2021-61651
DOI: https://doi.org/10.1115/PVP2021-61651
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Topics: Fatigue cracks, ASME Standards, Pressurized water reactors, Coolants, Electricity (Physics), Engineering standards, Fatigue, Japan Society of Mechanical Engineers, JSME Standards, Pipes
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

Experimental Investigation of Jet Cross-Flow Induced Vibration of a Rod Bundle

Ibrahim Gad-el-Hak, Njuki Mureithi, Kostas Karazis, Gary Williams
Proc. ASME. PVP2021, Volume 3: Fluid Structure Interaction; High Pressure Technology, V003T04A014, July 13–15, 2021
Paper No: PVP2021-65000
DOI: https://doi.org/10.1115/PVP2021-65000
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Topics: Accidents, Coolants, Cross-flow, Fuel rods, Jets, Pressurized water reactors, Vibration
Proceedings Papers

Investigation of the Irradiation Effect on the Dynamics of Nuclear Fuel Bundles

Osama Elbanhawy, Marwan Hassan, Atef Mohany, Hossam Kishawy
Proc. ASME. PVP2021, Volume 3: Fluid Structure Interaction; High Pressure Technology, V003T04A007, July 13–15, 2021
Paper No: PVP2021-62412
DOI: https://doi.org/10.1115/PVP2021-62412
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Topics: Dynamics (Mechanics), Fuel rods, Irradiation (Radiation exposure), Fuels, Flow (Dynamics), Constitutive equations, Coolants, Dynamic response, Mechanical properties, Pressure
Proceedings Papers

Elimination of BWR Mark I Program Primary Containment Drywell-to-Wetwell Differential Pressure

Raymond M. Pace, Jason Ritzel
Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A045, August 3, 2020
Paper No: PVP2020-21001
DOI: https://doi.org/10.1115/PVP2020-21001
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Topics: Boiling water reactors, Containment, Pressure, Vents, Accidents, Nitrogen, Water, Control rooms, Filters, Pipes
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

SCC Growth Prediction for Surface Crack in Welded Joint Using Advanced FEA

Takuya Ogawa, Masao Itatani, Takahiro Hayashi, Toshiyuki Saito
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A080, August 3, 2020
Paper No: PVP2020-21670
DOI: https://doi.org/10.1115/PVP2020-21670
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Topics: Finite element analysis, Surface cracks, Welded joints, Fracture (Materials), Fracture (Process), Shapes, Fitness-for-service, Metals, Stainless steel, Base metals
Proceedings Papers

Comparative Evaluation of Plastic Design Methods for Fatigue Assessment of a Nuclear Class 1 Piping Nozzle

David M. Clarkson, Christopher D. Bell, Donald Mackenzie
Proc. ASME. PVP2020, Volume 3: Design and Analysis, V003T03A043, August 3, 2020
Paper No: PVP2020-21271
DOI: https://doi.org/10.1115/PVP2020-21271
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Topics: Design methodology, Fatigue, Nozzles, Pipes, Design, Finite element analysis, ASME Boiler and Pressure Vessel Code, Pressurized water reactors, Stress, Coolants
Proceedings Papers

Crack Propagation Modeling in a PWR Under PTS Using XFEM

Diego F. Mora, Markus Niffenegger, Roman Mukin
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A001, August 3, 2020
Paper No: PVP2020-21026
DOI: https://doi.org/10.1115/PVP2020-21026
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Topics: Crack propagation, Modeling, Pressurized water reactors, Fracture (Materials), Damage, Finite element analysis, Fracture toughness, Accidents, Cooling, Simulation
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

Arnaud Blouin, Stéphane Marie, Tomas Nicak, Antti Timperi, Peter Gill
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A046, August 3, 2020
Paper No: PVP2020-21551
DOI: https://doi.org/10.1115/PVP2020-21551
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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 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
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Topics: Pipes, Fracture (Materials), Fracture (Process), Coolants, Ductile fracture, Fracture mechanics, Nuclear reactors, Pressure, Simulation, Stress
Proceedings Papers

Finite Element Verification of Engineering Equations for Prediction of Structural Strength of Annulus Spacers in CANDU Nuclear Reactors

Preeti Doddihal, Dennis Kawa, Douglas Scarth, Yu Chen
Proc. ASME. PVP2019, Volume 6A: Materials and Fabrication, V06AT06A013, July 14–19, 2019
Paper No: PVP2019-93671
DOI: https://doi.org/10.1115/PVP2019-93671
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Topics: Annulus, Finite element analysis, Nuclear reactors, Fracture (Materials), Fracture (Process), Strips, Fuels, Irradiation (Radiation exposure), Pressure, Stress
Proceedings Papers

Fast Reactor Core Seismic Analysis for Verification of Assessment Model Considering Deformation of Core Elements

Shinichiro Matsubara, Akihisa Iwasaki, Kazuteru Kawamura, Hidenori Harada, Tomohiko Yamamoto
Proc. ASME. PVP2019, Volume 8: Seismic Engineering, V008T08A041, July 14–19, 2019
Paper No: PVP2019-93778
DOI: https://doi.org/10.1115/PVP2019-93778
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Topics: Deformation, Fast neutron reactors, Seismic analysis, Vibration, Vibration tests, Displacement, Fluid structure interaction, Fluids, Irradiation (Radiation exposure), Thermal expansion
Proceedings Papers

European Project ATLAS+: Status of the WP1 Relative to the Experimental Program on Pipes and Specimens

Patrick Le Delliou, Dominique Moinereau, Myriam Bourgeois, Szabolcs Szavai
Proc. ASME. PVP2019, Volume 6A: Materials and Fabrication, V06AT06A043, July 14–19, 2019
Paper No: PVP2019-93505
DOI: https://doi.org/10.1115/PVP2019-93505
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Topics: Pipes, Fracture mechanics, Steel, Coolants, Design, Materials characterization, Materials properties, Metals, Nuclear reactors, Pressure
Proceedings Papers

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

Stéphane Marie, Arnaud Blouin, Tomas Nicak, Dominique Moinereau, Anna Dahl, Patrick Le Delliou, Myriam Bourgeois
Proc. ASME. PVP2019, Volume 6A: Materials and Fabrication, V06AT06A046, July 14–19, 2019
Paper No: PVP2019-93580
DOI: https://doi.org/10.1115/PVP2019-93580
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Topics: Coolants, Fracture (Materials), Fracture toughness, Leak-before-break, Modeling, Nuclear reactors, Pipes, Pressure, Residual stresses
Proceedings Papers

Assessment of Structural Integrity on Irradiated Steel Structure: Focusing on Long Column Type Reactor Pressure Vessel Supports

Goeun Han, Sukru Guzey
Proc. ASME. PVP2019, Volume 6B: Materials and Fabrication, V06BT06A020, July 14–19, 2019
Paper No: PVP2019-93640
DOI: https://doi.org/10.1115/PVP2019-93640
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Topics: Reactor vessels, Steel, Fitness-for-service, Neutrons, Irradiation (Radiation exposure), American Petroleum Institute, Coolants, Finite element model, Fluence (Radiation measurement), Fracture toughness
Proceedings Papers

Fatigue Initiation of 304L Stainless Steel Subject to Thermal Shock Loading in a PWR Environment

Peter Gill, Peter Brown, David Tice, Norman Platts, Chris Currie
Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A023, July 14–19, 2019
Paper No: PVP2019-93923
DOI: https://doi.org/10.1115/PVP2019-93923
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Topics: Fatigue, Pressurized water reactors, Stainless steel, Thermal shock, Cycles, Temperature, Transients (Dynamics), Stress, Testing, Design
Proceedings Papers

Effect of Coolant Water Temperature of ECCS on Failure Probability of RPV

Jinya Katsuyama, Koichi Masaki, Kai Lu, Tadashi Watanabe, Yinsheng Li
Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A059, July 14–19, 2019
Paper No: PVP2019-93967
DOI: https://doi.org/10.1115/PVP2019-93967
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Topics: Coolants, Emergency core cooling systems, Failure, Fracture mechanics, Probability, Thermal shock, Water temperature, Temperature, Pressure, Pressurized water reactors
Proceedings Papers

Advances Towards Elastic-Perfectly Plastic Simulation of the Core of Printed Circuit Heat Exchangers

Alon Katz, Devesh Ranjan
Proc. ASME. PVP2019, Volume 3: Design and Analysis, V003T03A093, July 14–19, 2019
Paper No: PVP2019-93807
DOI: https://doi.org/10.1115/PVP2019-93807
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Topics: Circuits, Heat exchangers, Simulation, Stress, Algorithms, ASME Standards, Brayton cycle, Computer simulation, Computer software, Coolants
Proceedings Papers

Vibration of a High Energy PWR Piping System due to Vibro-Acoustic Coupling: Evaluation and Mitigation

Gregory A. Meyer, Timothy K. Meneely, Jeremy R. Koether, Stephen D. Smith, David C. DiBasilio
Proc. ASME. PVP2019, Volume 4: Fluid-Structure Interaction, V004T04A021, July 14–19, 2019
Paper No: PVP2019-93594
DOI: https://doi.org/10.1115/PVP2019-93594
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Topics: Acoustics, Piping systems, Pressurized water reactors, Vibration, Pipes, Flow (Dynamics), Resonance, Boiling water reactors, Excitation, Junctions