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Proceedings Papers

Fracture Analysis of Reactor Pressure Vessel Lower Head Considering Core Meltdown Accident

Yaroslav Dubyk, Vitalii Antonchenko, Maksym Zarazovskii
Proc. ASME. PVP2021, Volume 2: Computer Technology and Bolted Joints; Design and Analysis, V002T03A063, July 13–15, 2021
Paper No: PVP2021-62062
DOI: https://doi.org/10.1115/PVP2021-62062
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Topics: Accidents, Fracture (Materials), Reactor vessels, Vessels, Boundary-value problems, Cavities, Cooling, Creep, Floods, Fracture mechanics
Proceedings Papers

NuScale Pressure and Temperature Limits Methodology Using Finite Element Analysis

Heqin Xu, Joe Remic, Hongqing Xu
Proc. ASME. PVP2021, Volume 2: Computer Technology and Bolted Joints; Design and Analysis, V002T03A018, July 13–15, 2021
Paper No: PVP2021-61856
DOI: https://doi.org/10.1115/PVP2021-61856
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Topics: Finite element analysis, Fracture mechanics, Pressure, Temperature, Brittleness, Cylinders, Design, Ductility, Failure, Finite element model
Proceedings Papers

An Application of the Brittle Fracture Criterion Gp Method to a RPV Type Geometry – Towards the Industrialization of the Method

Bin Zheng, Han Liu, Samuel Jules, Hai Xie, Kaikai Shi
Proc. ASME. PVP2021, Volume 2: Computer Technology and Bolted Joints; Design and Analysis, V002T03A045, July 13–15, 2021
Paper No: PVP2021-61636
DOI: https://doi.org/10.1115/PVP2021-61636
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Topics: Brittle fracture, Geometry, Fracture (Materials), China, Computer software, Damage, Energy conservation, Finite element analysis, Irradiation (Radiation exposure), Life extension
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

Coupling of Neutron Noise and Dynamic Finite Element Analyses to Perform Remote Condition Monitoring for Reactor Vessel Internals

Gregory A. Banyay, Matthew J. Palamara, Stephen D. Smith
Proc. ASME. PVP2021, Volume 3: Fluid Structure Interaction; High Pressure Technology, V003T04A006, July 13–15, 2021
Paper No: PVP2021-62201
DOI: https://doi.org/10.1115/PVP2021-62201
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Topics: Condition monitoring, Finite element analysis, Heat shielding, Machine learning, Neutrons, Noise (Sound), Reactor vessels, Structural dynamics, Structural health monitoring
Proceedings Papers

Evaluation of an Alloy 52 / Cladded Carbon Steel Repair Weld by Cold Metal Transfer

Caitlin Huotilainen, Heikki Keinänen, Juha Kuutti, Pekka Nevasmaa, Henrik Sirén, Iikka Virkkunen
Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A048, July 13–15, 2021
Paper No: PVP2021-61981
DOI: https://doi.org/10.1115/PVP2021-61981
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Topics: Alloys, Carbon steel, Maintenance, Metals, Reactor vessels, Welding
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

Study on Fracture Behavior and Assessment for Dissimilar Metal Weld of Low Alloy Steel and Ni-Base Alloy Weld Using a BWR Reactor Pressure Vessel Material

Takahiro Hayashi, Takuya Ogawa, Shuichi Yoshida, Masao Itatani, Yasuhiro Hattori, Tetsushi Yamaoka, Shigeaki Tanaka, Toshiyuki Saito
Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A047, July 13–15, 2021
Paper No: PVP2021-61467
DOI: https://doi.org/10.1115/PVP2021-61467
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Topics: Alloy steel, Alloys, Boiling water reactors, Fracture (Materials), Fracture mechanics, Fracture toughness, Metals, Reactor vessels, Stress corrosion cracking
Proceedings Papers

Assessment of Residual Stress for Thick Butt-Welded Plate of a Reactor Pressure Vessel Steel

Yoosung Ha, Shigetaka Okano, Hisashi Takamizawa, Jinya Katsuyama, Masahito Mochizuki
Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A067, July 13–15, 2021
Paper No: PVP2021-61897
DOI: https://doi.org/10.1115/PVP2021-61897
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Topics: Drilling, Finite element analysis, Reactor vessels, Steel, Stress
Proceedings Papers

FRACTESUS Project: General Framework of Materials Selection and Testing Processes

Tomasz Brynk, Marlies Lambrecht, Inge Uytdenhouwen, Pentti Arffman, Eberhard Altstadt, Tom Petit
Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A066, July 13–15, 2021
Paper No: PVP2021-61906
DOI: https://doi.org/10.1115/PVP2021-61906
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Topics: Fracture toughness, Reactor vessels, Tension, Testing, Steel, Base metals, Computer simulation, Fracture mechanics, Materials testing, Nuclear power stations
Proceedings Papers

Dedicated CT Tests and Numerical Simulations to Assess Crack Arrest by Quasi-Laminar Flaws

Pierre Dulieu, Valéry Lacroix, Robert Gérard, Tomasz Brynk, Inge Uytdenhouwen, Rachid Chaouadi
Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A020, July 13–15, 2021
Paper No: PVP2021-60379
DOI: https://doi.org/10.1115/PVP2021-60379
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Topics: Computer simulation, Fracture (Materials), Fracture toughness, Reactor vessels, Stress, Accidents, Brittleness, Defense industry, Displacement, Engineering simulation
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

Effect of Plastic Constraint and Cladding on Semi-Elliptical Shaped Crack in Fracture Toughness Evaluation for a Reactor Pressure Vessel Steel

Masaki Shimodaira, Tohru Tobita, Yasuto Nagoshi, Kai Lu, Jinya Katsuyama
Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A057, July 13–15, 2021
Paper No: PVP2021-61725
DOI: https://doi.org/10.1115/PVP2021-61725
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Topics: Cladding systems (Building), Fracture (Materials), Fracture toughness, Reactor vessels, Steel
Proceedings Papers

Evaluation of Brittle Crack Arrest Toughness for Highly-Irradiated Reactor Pressure Vessel Steels

Keiko Iwata, Kuniki Hata, Tohru Tobita, Takatoshi Hirota, Hisashi Takamizawa, Yasuhiro Chimi, Yutaka Nishiyama
Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A059, July 13–15, 2021
Paper No: PVP2021-61893
DOI: https://doi.org/10.1115/PVP2021-61893
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Topics: Brittleness, Fracture (Materials), Fracture toughness, Notch testing, Reactor vessels, Steel
Proceedings Papers

Effect of Several Design Parameters on the Sealing Performance of Reactor Pressure Vessel

Liangang Zheng, Xue Mi, Kaikai Shi, Xiaoming Bai, Hai Xie, Bin Zheng, Xiaohuan Yu
Proc. ASME. PVP2020, Volume 3: Design and Analysis, V003T03A015, August 3, 2020
Paper No: PVP2020-21208
DOI: https://doi.org/10.1115/PVP2020-21208
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Topics: Design, Reactor vessels, Sealing (Process), Flanges, Pressure vessels, Separation (Technology), Springs, Finite element analysis, Nuclear power stations, Nuclear reactor coolants
Proceedings Papers

Coupling of Neutron Transport and Probabilistic Fracture Mechanics Codes for Analysis of Embrittled Reactor Pressure Vessels

Benjamin W. Spencer, William M. Hoffman, Benjamin S. Collins, Shane C. Henderson
Proc. ASME. PVP2020, Volume 3: Design and Analysis, V003T03A057, August 3, 2020
Paper No: PVP2020-21680
DOI: https://doi.org/10.1115/PVP2020-21680
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Topics: Embrittlement, Fluence (Radiation measurement), Fracture mechanics, Neutrons, Reactor vessels
Proceedings Papers

High Flux Reactor Continued Safe Operation: Time Limited Ageing Analyses

L. Stefanini, F. H. E. de Haan - de Wilde
Proc. ASME. PVP2020, Volume 8: Operations, Applications, and Components, V008T08A010, August 3, 2020
Paper No: PVP2020-21032
DOI: https://doi.org/10.1115/PVP2020-21032
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Topics: Biomedicine, Equipment qualification, Fatigue, Irradiation (Radiation exposure), Isotopes, Leak-before-break, Manufacturing, Nuclear reactors, Reactor vessels
Proceedings Papers

Evaluation of Pressure-Temperature Limit Curve Considering Revised Stress Intensity Factor Method

Yunjoo Lee, Hyosub Yoon, Kyuwan Kim, Jongmin Kim, Hyunmin Kim
Proc. ASME. PVP2020, Volume 8: Operations, Applications, and Components, V008T08A022, August 3, 2020
Paper No: PVP2020-21123
DOI: https://doi.org/10.1115/PVP2020-21123
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Topics: Nozzles, Pressure, Reactor vessels, Stress, Temperature
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

Fracture Mechanics Assessment of Reactor Pressure Vessel Irradiated Structural Steel for Short Column Type Supports and Neutron Shield Tank

Alexandria M. Carolan, J. Brian Hall, Stephen K. Longwell, F. Arzu Alpan, Gregory M. Imbrogno, Anees A. Udyawar, Scott Boggs, Steve Franzone, Charles Tomes, Beth Haluska
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A007, August 3, 2020
Paper No: PVP2020-21142
DOI: https://doi.org/10.1115/PVP2020-21142
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Topics: Fracture mechanics, Neutrons, Reactor vessels, Structural steel