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Proceedings Papers

Influence of High Temperature Water on AISI 304 and ER 347 Regarding Their Threshold Value

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Georg Veile, Michael Grimm, Stefan Weihe, Jürgen Rudolph
Proc. ASME. PVP2024, Volume 4: Materials & Fabrication, V004T06A047, July 28–August 2, 2024
Publisher: American Society of Mechanical Engineers
Paper No: PVP2024-121861
https://doi.org/10.1115/PVP2024-121861
View Paper titled, Influence of High Temperature Water on AISI 304 and ER 347 Regarding Their Threshold Value
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Topics: Boiling water reactors, Corrosion, Fatigue, Fatigue testing, High temperature, Pressurized water reactors, Water
Proceedings Papers

Technical Basis for Revision to Code Case N-702

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Matthew Walter, Kevin Wong, Nathaniel G. Cofie, Mo Uddin, Gary Dominguez
Proc. ASME. PVP2023, Volume 1: Codes & Standards, V001T01A004, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-107044
https://doi.org/10.1115/PVP2023-107044
View Paper titled, Technical Basis for Revision to Code Case N-702
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Topics: Acceptance criteria, ASME Standards, Boiling water reactors, Engineering standards, Failure, Feedwater, Fracture mechanics, In-service inspection, Inspection, Nozzles
Proceedings Papers

Development of Prediction Tool for Flow-Accelerated Corrosion: (3) Development and Validation of Prediction Software “FALSET” With Water Single-Phase FAC Data Obtained in Japanese BWR Plants

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Yuta Uchiyama, Ryo Morita, Kazutoshi Fujiwara, Kimitoshi Yoneda
Proc. ASME. PVP2023, Volume 6: Operations, Applications, & Components, V006T07A010, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-105848
https://doi.org/10.1115/PVP2023-105848
View Paper titled, Development of Prediction Tool for Flow-Accelerated Corrosion: (3) Development and Validation of Prediction Software “FALSET” With Water Single-Phase FAC Data Obtained in Japanese BWR Plants
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Topics: Boiling water reactors, Computer software, Corrosion, Flow (Dynamics), Oxygen, Pipes, Water
Proceedings Papers

Study on the Applicability of GTN Model on Fracture Evaluation for Plate Specimen With a Surface Crack Using a BWR Reactor Pressure Vessel Material

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Takuya Ogawa, Takahiro Hayashi, Shuichi Yoshida, Masao Itatani, Toshiyuki Saito
Proc. ASME. PVP2023, Volume 5: Materials & Fabrication, V005T06A062, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-107208
https://doi.org/10.1115/PVP2023-107208
View Paper titled, Study on the Applicability of GTN Model on Fracture Evaluation for Plate Specimen With a Surface Crack Using a BWR Reactor Pressure Vessel Material
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Topics: Alloys, Boiling water reactors, Damage mechanics, Fracture (Materials), Fracture mechanics, Reactor vessels, Stress corrosion cracking, Surface cracks
Proceedings Papers

Evaluation of the Inherent LBB Behavior of Small-Diameter Class 1 and 2 Nuclear Piping Systems

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Elizabeth Twombly, Lance Hill, Gery Wilkowski, Frederick Brust, Bruce Lin, Robert Tregoning
Proc. ASME. PVP2023, Volume 5: Materials & Fabrication, V005T06A042, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-107685
https://doi.org/10.1115/PVP2023-107685
View Paper titled, Evaluation of the Inherent LBB Behavior of Small-Diameter Class 1 and 2 Nuclear Piping Systems
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Topics: Leak-before-break, Pipes, Piping systems, Stress, Displacement, Fracture (Materials), Plasticity, Boiling water reactors, Design, Pressurized water reactors
Proceedings Papers

Damage Evaluations for BWR Lower Head in Severe Accident Based on Multi-Physics Simulations

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Jinya Katsuyama, Yoshihito Yamaguchi, Yoshiyuki Nemoto, Takuya Furuta, Yoshiyuki Kaji
Proc. ASME. PVP2022, Volume 4A: Materials and Fabrication, V04AT06A030, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-84609
https://doi.org/10.1115/PVP2022-84609
View Paper titled, Damage Evaluations for BWR Lower Head in Severe Accident Based on Multi-Physics Simulations
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Topics: Accidents, Boiling water reactors, Creep, Damage, Physics, Radiation (Physics), Simulation, Thermal hydraulics
Proceedings Papers

Study on Ductile Crack Extension and Fracture Behavior in Plate Specimen With a Semi-Elliptical Surface Crack Using a BWR Reactor Pressure Vessel Material

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Takahiro Hayashi, Takuya Ogawa, Shuichi Yoshida, Masao Itatani, Toshiyuki Saito
Proc. ASME. PVP2022, Volume 4B: Materials and Fabrication, V04BT06A020, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-84606
https://doi.org/10.1115/PVP2022-84606
View Paper titled, Study on Ductile Crack Extension and Fracture Behavior in Plate Specimen With a Semi-Elliptical Surface Crack Using a BWR Reactor Pressure Vessel Material
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Topics: Boiling water reactors, Ductile fracture, Fracture (Materials), Fracture (Process), Fracture mechanics, Metals, Reactor vessels, Stress corrosion cracking, Surface cracks
Proceedings Papers

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

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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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-84747
https://doi.org/10.1115/PVP2022-84747
View Paper titled, Large-Scale Parametric Modeling of Spent Nuclear Fuel Dynamics in the 30 cm Package Drop Scenario
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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

Computational Fluid Dynamics Modeling of Dry Cask Simulator With Crosswind

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Ben J. Jensen, Sarah R. Suffield, Megan E. Higley
Proc. ASME. PVP2022, Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division, V005T07A026, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-84090
https://doi.org/10.1115/PVP2022-84090
View Paper titled, Computational Fluid Dynamics Modeling of Dry Cask Simulator With Crosswind
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Topics: Computational fluid dynamics, Modeling, Spent nuclear fuels, Stress corrosion cracking, Computer software, Sensitivity analysis, Spent fuel storage, Boiling water reactors, Containment vessels, Flow (Dynamics)
Proceedings Papers

An Estimate of Spent Nuclear Fuel Mechanical Loads in the General 30 cm Package Drop Scenario

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Nicholas Klymyshyn, Kevin Kadooka, Casey Spitz, James Fitzpatrick
Proc. ASME. PVP2022, Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division, V005T07A028, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-84353
https://doi.org/10.1115/PVP2022-84353
View Paper titled, An Estimate of Spent Nuclear Fuel Mechanical Loads in the General 30 cm Package Drop Scenario
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Topics: Spent nuclear fuels, Stress, Fuels, Manufacturing, Damage, Modeling, Boiling water reactors, Boundary element methods, Collaboration, Design
Proceedings Papers

Seismic Test Results of the Main Steam Isolation Valve for Japanese Boiling Water Reactor Nuclear Power Plants (Part 2)

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Hideaki Itabashi, Yoshitaka Tsutsumi, Koji Nishino, Shin Kumagai, Ryo Kubota, Shota Tanemura
Proc. ASME. PVP2022, Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division, V005T08A005, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-84190
https://doi.org/10.1115/PVP2022-84190
View Paper titled, Seismic Test Results of the Main Steam Isolation Valve for Japanese Boiling Water Reactor Nuclear Power Plants (Part 2)
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Topics: Boiling water reactors, Nuclear power stations, Steam, Valves
Proceedings Papers

Probabilistic Fracture Mechanics Evaluation of a BWR Feedwater Nozzle

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Kevin K. L. Wong, Garivalde Dominguez, Do Jun Shim, Steven K. Richter
Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A031, July 13–15, 2021
Publisher: American Society of Mechanical Engineers
Paper No: PVP2021-62933
https://doi.org/10.1115/PVP2021-62933
View Paper titled, Probabilistic Fracture Mechanics Evaluation of a BWR Feedwater Nozzle
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Topics: ASME Standards, Boiling water reactors, Feedwater, Fracture mechanics, Inspection, Nozzles, Shells
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

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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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2021-61467
https://doi.org/10.1115/PVP2021-61467
View Paper titled, 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
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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

Thermal Analysis Evaluations Using the Dry Cask Simulator

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S. R. Suffield, D. J. Richmond, J. A. Fort
Proc. ASME. PVP2021, Volume 5: Operations, Applications, and Components; Seismic Engineering; Non-Destructive Examination, V005T07A028, July 13–15, 2021
Publisher: American Society of Mechanical Engineers
Paper No: PVP2021-61846
https://doi.org/10.1115/PVP2021-61846
View Paper titled, Thermal Analysis Evaluations Using the Dry Cask Simulator
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Topics: Thermal analysis, Fuels, Manufacturing, Computational fluid dynamics, Storage, Cladding systems (Building), Geometry, Heat, Stress, Temperature
Proceedings Papers

Technical Basis for Code Case N-894 Alternative Rules for Repair of Classes 1, 2, and 3 Austenitic Stainless Steel Piping With Thermal Fatigue Cracking

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Stephen Marlette, Steven L. McCraken, Christopher Lohse
Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A097, August 3, 2020
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21544
https://doi.org/10.1115/PVP2020-21544
View Paper titled, Technical Basis for Code Case N-894 Alternative Rules for Repair of Classes 1, 2, and 3 Austenitic Stainless Steel Piping With Thermal Fatigue Cracking
Open the PDF for Technical Basis for Code Case N-894 Alternative Rules for Repair of Classes 1, 2, and 3 Austenitic Stainless Steel Piping With Thermal Fatigue Cracking in another window
Topics: Fatigue cracks, Maintenance, Pipes, Stainless steel, Overlays (Materials engineering), Fatigue, Boiling water reactors, Pressurized water reactors, Stress corrosion cracking, Design
Proceedings Papers

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

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Takuya Ogawa, Masao Itatani, Takahiro Hayashi, Toshiyuki Saito
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A080, August 3, 2020
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21670
https://doi.org/10.1115/PVP2020-21670
View Paper titled, SCC Growth Prediction for Surface Crack in Welded Joint Using Advanced FEA
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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

Investigation on the Effects of Carbon Macro-Segregation of Mechanical Properties Using a Large-Scale Forged Low Alloy Steel for a BWR Reactor Pressure Vessel

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Takahiro Hayashi, Takuya Ogawa, Rie Sumiya, Tetsushi Yamaoka, Shigeaki Tanaka, Yasuhiro Hattori, Atsushi Mori
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A082, August 3, 2020
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21857
https://doi.org/10.1115/PVP2020-21857
View Paper titled, Investigation on the Effects of Carbon Macro-Segregation of Mechanical Properties Using a Large-Scale Forged Low Alloy Steel for a BWR Reactor Pressure Vessel
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Topics: Alloy steel, Boiling water reactors, Carbon, Fracture toughness, Iron and steel making, Mechanical properties, Pressure vessels, Reactor vessels
Proceedings Papers

Applicability of Formula of the Irradiation Assisted Stress Corrosion Cracking Rates for Neutron-Irradiated Type 316L Stainless Steels to Various Types of Stainless Steels Under Boiling Water Reactor Condition

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Masato Koshiishi, Hitoshi Seto, Shigeaki Tanaka, Ryoji Obata
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A073, August 3, 2020
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21332
https://doi.org/10.1115/PVP2020-21332
View Paper titled, Applicability of Formula of the Irradiation Assisted Stress Corrosion Cracking Rates for Neutron-Irradiated Type 316L Stainless Steels to Various Types of Stainless Steels Under Boiling Water Reactor Condition
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Topics: Boiling water reactors, Irradiation (Radiation exposure), Neutrons, Stainless steel, Stress corrosion cracking, Fracture (Materials), Grain boundaries, Mechanical properties
Proceedings Papers

Bounding Acoustic Load Development for Boiling Water Reactor Shroud and Shroud Supports

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Matthew Walter, Minghao Qin, Daniel Sommerville
Proc. ASME. PVP2020, Volume 4: Fluid-Structure Interaction, V004T04A009, August 3, 2020
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21633
https://doi.org/10.1115/PVP2020-21633
View Paper titled, Bounding Acoustic Load Development for Boiling Water Reactor Shroud and Shroud Supports
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Topics: Boiling water reactors, Sound pressure
Proceedings Papers

Thermal Analysis Evaluations Using the Dry Cask Simulator

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S. R. Suffield, D. J. Richmond, J. A. Fort
Proc. ASME. PVP2020, Volume 8: Operations, Applications, and Components, V008T08A037, August 3, 2020
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21146
https://doi.org/10.1115/PVP2020-21146
View Paper titled, Thermal Analysis Evaluations Using the Dry Cask Simulator
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Topics: Thermal analysis, Fuels, Manufacturing, Computational fluid dynamics, Storage, Cladding systems (Building), Geometry, Heat, Stress, Temperature