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Proceedings Papers

Overview of Particle Deposition Models for Spent Nuclear Fuel Storage Systems

Sarah R. Suffield, Philip J. Jensen, William A. Perkins, Ben J. Jensen, Christopher L. Grant, Casey Spitz
Proc. ASME. PVP2022, Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division, V005T07A025, July 17–22, 2022
Paper No: PVP2022-83982
DOI: https://doi.org/10.1115/PVP2022-83982
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Topics: Particulate matter, Spent fuel storage, Stress corrosion cracking, Storage, Computational fluid dynamics, Modeling, Spent nuclear fuels, Heat, Inspection, Nuclear power
Proceedings Papers

Analytical Method for Evaluating a 4-Piece Retaining Ring

Alton Reich, Roberto DiSalvo
Proc. ASME. PVP2022, Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division, V005T07A018, July 17–22, 2022
Paper No: PVP2022-83675
DOI: https://doi.org/10.1115/PVP2022-83675
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Topics: Analytical methods, Design, Nuclear power, Nuclear power stations, Pressure, Shapes, Valves
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

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

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

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

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

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

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

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

Development of Probabilistic Fracture Mechanics Analysis Code PASCAL Version 4 for Reactor Pressure Vessels

Kai Lu, Koichi Masaki, Jinya Katsuyama, Yinsheng Li, Shumpei Uno
Proc. ASME. PVP2018, Volume 1B: Codes and Standards, V01BT01A003, July 15–20, 2018
Paper No: PVP2018-84964
DOI: https://doi.org/10.1115/PVP2018-84964
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Topics: Fracture mechanics, Reactor vessels, Embrittlement, Failure, Irradiation (Radiation exposure), Stress, Computational methods, Light water reactors, Neutrons, Nuclear power
Proceedings Papers

Sensitivity Study on the Effects of Nondestructive Examinations on Failure Probabilities of Reactor Pressure Vessels

Kensaku Arai, Jinya Katsuyama, Yinsheng Li
Proc. ASME. PVP2018, Volume 1B: Codes and Standards, V01BT01A058, July 15–20, 2018
Paper No: PVP2018-84989
DOI: https://doi.org/10.1115/PVP2018-84989
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Topics: Failure, Probability, Reactor vessels, Flaw detection, Embrittlement, Fracture (Materials), Fracture (Process), Fracture mechanics, Irradiation (Radiation exposure), Manufacturing
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