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Proceedings Papers

Safety Justification Strategy for the Implementation of Additive Manufacture Small-Bore Globe Valves for Nuclear Plant

Bill Press, Adam Dukes, Dave Poole, Jack Adams, Luke Burling, John Sulley

Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A006, July 13–15, 2021

Paper No: PVP2021-62614

DOI: https://doi.org/10.1115/PVP2021-62614

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Topics: Nuclear power stations, Safety, Valves, Hardening, Pressure testing, Additive manufacturing, Bond strength, Cobalt, Construction, Dynamic testing (Materials)

Proceedings Papers

Benchmark Analysis by Beremin Model and GTN Model in CAF Subcommittee

Takatoshi Hirota, Yasuto Nagoshi, Kiminobu Hojo, Hiroshi Okada, Akiyuki Takahashi, Jinya Katsuyama, Takashi Ueda, Takuya Ogawa, Kenji Yashirodai, Mitsuru Ohata, Fumiyoshi Minami

Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A056, July 13–15, 2021

Paper No: PVP2021-61668

DOI: https://doi.org/10.1115/PVP2021-61668

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Topics: Brittleness, Computer simulation, Damage, Deformation, Ductile fracture, Ductile-brittle transition, Evaluation methods, Finite element analysis, Finite element model, Flat plates

Proceedings Papers

A Hybrid Fatigue Analysis Method for Fatigue Monitor System

Xiaoming Bai, Hai Xie, Kaikai Shi, Honglei Ai, Liangang Zheng, Xue Mi

Proc. ASME. PVP2020, Volume 8: Operations, Applications, and Components, V008T08A011, August 3, 2020

Paper No: PVP2020-21180

DOI: https://doi.org/10.1115/PVP2020-21180

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Topics: Fatigue, Fatigue analysis, Transients (Dynamics), Cycles, Stress, Design, Nuclear power stations, Databases, China, Finite element methods

Proceedings Papers

Research on the Seismic Analysis and Optimization of High Flux Reactor Nuclear Power Piping System Based on Multi-Point Response Spectrum Method

Xuan Huang, Pingchuan Shen, Shuai Liu, Jian Liu, Xiaozhou Jiang, Xiaofei Yu, Hai Xie, Kaikai Shi, Yuanyuan Ji

Proc. ASME. PVP2020, Volume 9: Seismic Engineering, V009T09A015, August 3, 2020

Paper No: PVP2020-21040

DOI: https://doi.org/10.1115/PVP2020-21040

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Topics: Nuclear power, Optimization, Piping systems, Seismic analysis

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

Study on Incorporation of New Design Fatigue Curves and a New Environmental Fatigue Correction Factor for PWR Environment Into the JSME Environmental Fatigue Evaluation Method

Seiji Asada, Shengde Zhang, Masahiro Takanashi, Yuichiro Nomura

Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A009, August 3, 2020

Paper No: PVP2020-21078

DOI: https://doi.org/10.1115/PVP2020-21078

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Topics: Design, Evaluation methods, Fatigue, Japan Society of Mechanical Engineers, Pressurized water reactors, Stainless steel, Base metals, Fatigue analysis, Metals, Fatigue testing

Proceedings Papers

Extension of PASCAL4 Code for Probabilistic Fracture Mechanics Analysis of Reactor Pressure Vessel in Boiling Water Reactor

Kai Lu, Jinya Katsuyama, Yinsheng Li

Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A062, August 3, 2020

Paper No: PVP2020-21421

DOI: https://doi.org/10.1115/PVP2020-21421

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Topics: Boiling water reactors, Fracture mechanics, Reactor vessels, Transients (Dynamics), Fracture (Materials), Pressurized water reactors, Surface cracks, Computational methods, Embrittlement, Irradiation (Radiation exposure)

Proceedings Papers

Probabilistic Fracture Mechanics Benchmarking Study Involving the xLPR and PASCAL-SP Codes: Analysis by PASCAL-SP

Akihiro Mano, Jinya Katsuyama, Yinsheng Li

Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A063, August 3, 2020

Paper No: PVP2020-21427

DOI: https://doi.org/10.1115/PVP2020-21427

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Topics: Fracture mechanics, Stress corrosion cracking, Water, Stress, Boiling water reactors, Collaboration, Failure, Fatigue, Nuclear power, Nuclear power stations

Proceedings Papers

A52M/SA52 Dissimilar Metal RPV Repair Weld: Experimental Evaluation and Post-Weld Characterizations

Iikka Virkkunen, Mikko Peltonen, Henrik Sirén, Pekka Nevasmaa, Caitlin Huotilainen, Heikki Keinänen, Juha Kuutti, Aloshious Lambai, Gaurav Mohanty, Mari Honkanen

Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A110, August 3, 2020

Paper No: PVP2020-21236

DOI: https://doi.org/10.1115/PVP2020-21236

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Topics: Maintenance, Metals, Welding, Cracking (Materials), Fracture (Process), Reactor vessels, Alloys, Fracture (Materials), Heat, Alloy steel

Proceedings Papers

Application of Probabilistic Fracture Mechanics Methodology for Japanese Reactor Pressure Vessels Using PASCAL4

Kai Lu, Jinya Katsuyama, Yinsheng Li, Shinobu Yoshimura

Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A057, July 14–19, 2019

Paper No: PVP2019-93935

DOI: https://doi.org/10.1115/PVP2019-93935

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Topics: Fracture mechanics, Reactor vessels, Failure, Neutrons, Embrittlement, Fluence (Radiation measurement), Irradiation (Radiation exposure), Light water reactors, Nondestructive evaluation, Nuclear power

Proceedings Papers

RPV Irradiation Surveillance Programmes in China

Shuo Zhang, Haisheng Zhang, Kai Sun

Proc. ASME. PVP2019, Volume 6A: Materials and Fabrication, V06AT06A025, July 14–19, 2019

Paper No: PVP2019-93068

DOI: https://doi.org/10.1115/PVP2019-93068

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Topics: China, Irradiation (Radiation exposure), Surveillance, Pressurized water reactors, Safety, Nuclear power, Nuclear power stations, Construction, Design, Embrittlement

Proceedings Papers

Development of New Design Fatigue Curves in Japan: Discussion of Crack Growth Behavior in Large-Scale Fatigue Tests of Carbon and Low-Alloy Steel Plates

Masahiro Takanashi, Hiroshi Ueda, Toshiyuki Saito, Takuya Ogawa, Kentaro Hayashi

Proc. ASME. PVP2019, Volume 3: Design and Analysis, V003T03A051, July 14–19, 2019

Paper No: PVP2019-93393

DOI: https://doi.org/10.1115/PVP2019-93393

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Topics: Alloys, Carbon, Design, Fatigue, Fatigue testing, Fracture (Materials), Plates (structures), Steel, Stress, Fatigue cracks

Proceedings Papers

Development of New Design Fatigue Curves in Japan: Discussion of Fatigue Crack Growth Based on Fatigue Test Data With Large Scale Piping

Masaru Bodai, Yuichi Fukuta, Seiji Asada, Kentaro Hayashi

Proc. ASME. PVP2019, Volume 3: Design and Analysis, V003T03A049, July 14–19, 2019

Paper No: PVP2019-93272

DOI: https://doi.org/10.1115/PVP2019-93272

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Topics: Design, Fatigue, Fatigue cracks, Fatigue testing, Pipes, Stainless steel, Fracture (Materials), Stress, Alloy steel, Carbon steel

Proceedings Papers

Study on Incorporation of a New Design Fatigue Curve Into the JSME Environmental Fatigue Evaluation Method

Seiji Asada, Shengde Zhang, Masahiro Takanashi, Yuichirou Nomura

Proc. ASME. PVP2019, Volume 3: Design and Analysis, V003T03A050, July 14–19, 2019

Paper No: PVP2019-93273

DOI: https://doi.org/10.1115/PVP2019-93273

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Topics: Design, Evaluation methods, Fatigue, Japan Society of Mechanical Engineers, Fatigue analysis, Nuclear power, Energy generation, Welding

Proceedings Papers

Investigations of In-Plane Fluidelastic Instability in a Multi-Span U-Bend Test Rig: Tests in Two-Phase Flow

Paul Feenstra, Teguewinde Sawadogo, Bruce Smith, Victor Janzen, Anne McLellan, Helen Cothron, Sean Kil

Proc. ASME. PVP2019, Volume 4: Fluid-Structure Interaction, V004T04A025, July 14–19, 2019

Paper No: PVP2019-93729

DOI: https://doi.org/10.1115/PVP2019-93729

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Topics: Accelerometers, Boilers, Cross-flow, Damage, Displacement, Electricity (Physics), Flow (Dynamics), Geometry, Nuclear power, Porosity

Proceedings Papers

Verification of Probabilistic Fracture Mechanics Analysis Code Through Benchmark Analyses

Yinsheng Li, Shumpei Uno, Koichi Masaki, Jinya Katsuyama, Terry Dickson, Mark Kirk

Proc. ASME. PVP2018, Volume 1B: Codes and Standards, V01BT01A075, July 15–20, 2018

Paper No: PVP2018-84963

DOI: https://doi.org/10.1115/PVP2018-84963

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Topics: Fracture mechanics, Failure, Probability, Embrittlement, Irradiation (Radiation exposure), Neutrons, Nuclear power, Reactor vessels, Thermal shock

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

Development of New Design Fatigue Curves in Japan: Discussion of Best Fit Curves Based on Fatigue Test Data With Large Scale Piping

Masaru Bodai, Yuichi Fukuta, Seiji Asada, Kentaro Hayashi

Proc. ASME. PVP2018, Volume 3B: Design and Analysis, V03BT03A005, July 15–20, 2018

Paper No: PVP2018-84436

DOI: https://doi.org/10.1115/PVP2018-84436

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Topics: Design, Fatigue, Fatigue testing, Pipes, Stainless steel, Alloy steel, Carbon steel, Databases, Stress, Surface finishing

Proceedings Papers

Development of New Design Fatigue Curves in Japan: Discussion of Best-Fit Curves Based on Large-Scale Fatigue Tests of Carbon and Low-Alloy Steel Plates

Masahiro Takanashi, Hiroshi Ueda, Toshiyuki Saito, Takuya Ogawa, Kentaro Hayashi

Proc. ASME. PVP2018, Volume 3B: Design and Analysis, V03BT03A006, July 15–20, 2018

Paper No: PVP2018-84456

DOI: https://doi.org/10.1115/PVP2018-84456

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Topics: Alloys, Carbon, Design, Fatigue, Fatigue testing, Plates (structures), Steel, Fracture (Materials), Carbon steel, Cycles

Proceedings Papers

Development of New Design Fatigue Curves in Japan: Proposal of a New Fatigue Evaluation Method

Seiji Asada, Akihiko Hirano, Toshiyuki Saito, Yasukazu Takada, Hideo Kobayashi

Proc. ASME. PVP2018, Volume 3B: Design and Analysis, V03BT03A004, July 15–20, 2018

Paper No: PVP2018-84432

DOI: https://doi.org/10.1115/PVP2018-84432

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Topics: Design, Evaluation methods, Fatigue, Alloys, Stainless steel, Steel, Carbon steel, Fatigue testing, Databases, Finishes

2 3 4 5

NARROW

Safety Justification Strategy for the Implementation of Additive Manufacture Small-Bore Globe Valves for Nuclear Plant

Benchmark Analysis by Beremin Model and GTN Model in CAF Subcommittee

A Hybrid Fatigue Analysis Method for Fatigue Monitor System

Research on the Seismic Analysis and Optimization of High Flux Reactor Nuclear Power Piping System Based on Multi-Point Response Spectrum Method

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

Study on Incorporation of New Design Fatigue Curves and a New Environmental Fatigue Correction Factor for PWR Environment Into the JSME Environmental Fatigue Evaluation Method

Extension of PASCAL4 Code for Probabilistic Fracture Mechanics Analysis of Reactor Pressure Vessel in Boiling Water Reactor

Probabilistic Fracture Mechanics Benchmarking Study Involving the xLPR and PASCAL-SP Codes: Analysis by PASCAL-SP

A52M/SA52 Dissimilar Metal RPV Repair Weld: Experimental Evaluation and Post-Weld Characterizations

Application of Probabilistic Fracture Mechanics Methodology for Japanese Reactor Pressure Vessels Using PASCAL4

RPV Irradiation Surveillance Programmes in China

Development of New Design Fatigue Curves in Japan: Discussion of Crack Growth Behavior in Large-Scale Fatigue Tests of Carbon and Low-Alloy Steel Plates

Development of New Design Fatigue Curves in Japan: Discussion of Fatigue Crack Growth Based on Fatigue Test Data With Large Scale Piping

Study on Incorporation of a New Design Fatigue Curve Into the JSME Environmental Fatigue Evaluation Method

Investigations of In-Plane Fluidelastic Instability in a Multi-Span U-Bend Test Rig: Tests in Two-Phase Flow

Verification of Probabilistic Fracture Mechanics Analysis Code Through Benchmark Analyses

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

Development of New Design Fatigue Curves in Japan: Discussion of Best Fit Curves Based on Fatigue Test Data With Large Scale Piping

Development of New Design Fatigue Curves in Japan: Discussion of Best-Fit Curves Based on Large-Scale Fatigue Tests of Carbon and Low-Alloy Steel Plates

Development of New Design Fatigue Curves in Japan: Proposal of a New Fatigue Evaluation Method

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