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Proceedings Papers

Development of the Buckling Evaluation Method for Large Scale Vessel in Fast Reactors by the Testing of Austenitic Stainless Steel Vessel With Severe Initial Imperfection Subjected to Horizontal and Vertical Loading

Takashi Okafuji, Kazuhiro Miura, Hiromi Sago, Hisatomo Murakami, Masanori Ando, Satoshi Okajima
Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A032, July 17–22, 2022
Paper No: PVP2022-84605
DOI: https://doi.org/10.1115/PVP2022-84605
View Paper titled, Development of the Buckling Evaluation Method for Large Scale Vessel in Fast Reactors by the Testing of Austenitic Stainless Steel Vessel With Severe Initial Imperfection Subjected to Horizontal and Vertical Loading
Click here to open pdf in another window PDF for Development of the Buckling Evaluation Method for Large Scale Vessel in Fast Reactors by the Testing of Austenitic Stainless Steel Vessel With Severe Initial Imperfection Subjected to Horizontal and Vertical Loading
Topics: Buckling, Evaluation methods, Fast neutron reactors, Stainless steel, Testing, Vessels, Steel, Stress, Design, Power stations
Proceedings Papers

Development of the Buckling Evaluation Method for Large Scale Vessel by the Testing of Gr. 91 Vessel Subjected to Horizontal and Cyclic Vertical Loading

Takashi Okafuji, Kazuhiro Miura, Hiromi Sago, Hisatomo Murakami, Masanori Ando, Masashi Miyazaki
Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A016, July 13–15, 2021
Paper No: PVP2021-60672
DOI: https://doi.org/10.1115/PVP2021-60672
View Paper titled, Development of the Buckling Evaluation Method for Large Scale Vessel by the Testing of Gr. 91 Vessel Subjected to Horizontal and Cyclic Vertical Loading
Click here to open pdf in another window PDF for Development of the Buckling Evaluation Method for Large Scale Vessel by the Testing of Gr. 91 Vessel Subjected to Horizontal and Cyclic Vertical Loading
Topics: Buckling, Evaluation methods, Testing, Vessels, Stress, Shapes, Design, Fast neutron reactors, Plates (structures), Power stations
Proceedings Papers

Overview of EASICS Weldment Assessment Route Development Through Inelastic Analysis

S. May, S. Bate, M. Chevalier, D. Dean
Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A092, August 3, 2020
Paper No: PVP2020-21717
DOI: https://doi.org/10.1115/PVP2020-21717
View Paper titled, Overview of EASICS Weldment Assessment Route Development Through Inelastic Analysis
Click here to open pdf in another window PDF for Overview of EASICS Weldment Assessment Route Development Through Inelastic Analysis
Topics: Creep, Fatigue, Finite element analysis, Geometry, High temperature, Inelastic analysis, Metalwork, Nuclear design, Plant design, Steel
Proceedings Papers

2025 Nuclear Code: The Vision for the Future of ASME Nuclear Codes and Standards

Dale E. Matthews, Ralph S. Hill, Charles W. Bruny
Proc. ASME. PVP2018, Volume 1B: Codes and Standards, V01BT01A008, July 15–20, 2018
Paper No: PVP2018-84031
DOI: https://doi.org/10.1115/PVP2018-84031
View Paper titled, 2025 Nuclear Code: The Vision for the Future of ASME Nuclear Codes and Standards
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Topics: Engineering standards, Construction, Light water reactors, Plant design, Safety, Design, Fatigue, Finite element analysis, High temperature, Inspection
Proceedings Papers

Structural Stability Evaluation of Independent Spent Fuel Storage Casks

Gunup Kwon, Phuong Hoang, Khaled Ata
Proc. ASME. PVP2018, Volume 8: Seismic Engineering, V008T08A017, July 15–20, 2018
Paper No: PVP2018-84602
DOI: https://doi.org/10.1115/PVP2018-84602
View Paper titled, Structural Stability Evaluation of Independent Spent Fuel Storage Casks
Click here to open pdf in another window PDF for Structural Stability Evaluation of Independent Spent Fuel Storage Casks
Topics: Spent fuel storage, Structural stability, Dynamic analysis, Stability, Concretes, Earthquakes, Fuels, Nuclear power stations, Plant design, Power stations
Proceedings Papers

Dynamic Material Test and Analysis for Rupture Study for Pressure Vessel Exposed to Fire in Plant

Tetsuya Kawai, Yasuhiro Mitarai, Yoshiyuki Waki, Yoko Yamabe-Mitarai, Kazuhiro Kimura, Kazuyuki Kasuya
Proc. ASME. PVP2017, Volume 3A: Design and Analysis, V03AT03A063, July 16–20, 2017
Paper No: PVP2017-65246
DOI: https://doi.org/10.1115/PVP2017-65246
View Paper titled, Dynamic Material Test and Analysis for Rupture Study for Pressure Vessel Exposed to Fire in Plant
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Topics: Fire, Pressure vessels, Rupture, Design, Finite element methods, Finite element model, Materials testing, Pressure, Vessels, Carbon steel
Proceedings Papers

Effect of Variable Temperature on the Fatigue Life and Crack Growth Rates of Austenitic Stainless Steels in PWR Coolant Environments

N. Platts, P. Gill, S. Cruchley, E. Grieveson, M. Twite
Proc. ASME. PVP2017, Volume 1A: Codes and Standards, V01AT01A029, July 16–20, 2017
Paper No: PVP2017-66029
DOI: https://doi.org/10.1115/PVP2017-66029
View Paper titled, Effect of Variable Temperature on the Fatigue Life and Crack Growth Rates of Austenitic Stainless Steels in PWR Coolant Environments
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Topics: Coolants, Fatigue life, Fracture (Materials), Pressurized water reactors, Stainless steel, Temperature, Fatigue, Transients (Dynamics), Fatigue cracks, Stress
Proceedings Papers

Nuclear Power Plant Fires and Explosions: Part I — Plant Designs and Hydrogen Ignition

Robert A. Leishear
Proc. ASME. PVP2017, Volume 4: Fluid-Structure Interaction, V004T04A014, July 16–20, 2017
Paper No: PVP2017-66285
DOI: https://doi.org/10.1115/PVP2017-66285
View Paper titled, Nuclear Power Plant Fires and Explosions: Part I — Plant Designs and Hydrogen Ignition
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Topics: Explosions, Fire, Hydrogen, Ignition, Nuclear power stations, Plant design, Pressurized water reactors, Accidents, Boiling water reactors, Chernobyl Nuclear Accident, Chornobyl, Ukraine, 1986
Proceedings Papers

Calculation and Analysis for Pressure Vessel Rupture Study Under Fire in Plant

Yoshiyasu Ito, Akira Tsuruoka, Yoshiyuki Waki, Hiroko Osedo
Proc. ASME. PVP2016, Volume 3: Design and Analysis, V003T03A033, July 17–21, 2016
Paper No: PVP2016-63184
DOI: https://doi.org/10.1115/PVP2016-63184
View Paper titled, Calculation and Analysis for Pressure Vessel Rupture Study Under Fire in Plant
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Topics: Fire, Pressure vessels, Rupture, Design, Carbon steel, Pressure, Stainless steel, Vessels, Computational methods, Finite element methods
Proceedings Papers

Flaw Tolerance Assessment for Low-Cycle Fatigue of Stainless Steel

Masayuki Kamaya
Proc. ASME. PVP2015, Volume 1A: Codes and Standards, V01AT01A050, July 19–23, 2015
Paper No: PVP2015-45104
DOI: https://doi.org/10.1115/PVP2015-45104
View Paper titled, Flaw Tolerance Assessment for Low-Cycle Fatigue of Stainless Steel
Click here to open pdf in another window PDF for Flaw Tolerance Assessment for Low-Cycle Fatigue of Stainless Steel
Topics: Low cycle fatigue, Stainless steel, Fracture (Materials), Design, Fatigue life, Fatigue, Fatigue damage, Inspection, Stress, ASME Boiler and Pressure Vessel Code
Proceedings Papers

A Rational Basis for Deterministic Margins in CUF-Based Fatigue Evaluation With Uncertainty

Y. S. Garud, David A. Steininger
Proc. ASME. PVP2015, Volume 1A: Codes and Standards, V01AT01A052, July 19–23, 2015
Paper No: PVP2015-45806
DOI: https://doi.org/10.1115/PVP2015-45806
View Paper titled, A Rational Basis for Deterministic Margins in CUF-Based Fatigue Evaluation With Uncertainty
Click here to open pdf in another window PDF for A Rational Basis for Deterministic Margins in CUF-Based Fatigue Evaluation With Uncertainty
Topics: Fatigue, Uncertainty, Stress, Design, Fatigue damage, Light water reactors, Plant design, Power stations, Risk, Safety
Proceedings Papers

Fatigue Crack Initiation and Growth Observation for 316 Stainless Steel Subjected to Equi-Biaxial Cyclic Loading

Satoshi Iida, Shigeki Abe, Takao Nakamura, Masayuki Kamaya
Proc. ASME. PVP2015, Volume 3: Design and Analysis, V003T03A049, July 19–23, 2015
Paper No: PVP2015-45814
DOI: https://doi.org/10.1115/PVP2015-45814
View Paper titled, Fatigue Crack Initiation and Growth Observation for 316 Stainless Steel Subjected to Equi-Biaxial Cyclic Loading
Click here to open pdf in another window PDF for Fatigue Crack Initiation and Growth Observation for 316 Stainless Steel Subjected to Equi-Biaxial Cyclic Loading
Topics: Fatigue cracks, Stainless steel, Stress, Fracture (Materials), Fatigue damage, Fatigue, Fatigue testing, Cracking (Materials), Design, Disks
Proceedings Papers

Material Test and Analysis for Pressure Vessel Rupture Study Under Fire in Plant

Yoshiyasu Itoh, Yoshiyuki Waki, Kazuyuki Kasuya
Proc. ASME. PVP2015, Volume 3: Design and Analysis, V003T03A051, July 19–23, 2015
Paper No: PVP2015-45260
DOI: https://doi.org/10.1115/PVP2015-45260
View Paper titled, Material Test and Analysis for Pressure Vessel Rupture Study Under Fire in Plant
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Topics: Fire, Pressure vessels, Rupture, Design, Pressure, Carbon steel, Computational methods, Finite element methods, Finite element model, Fluids
Proceedings Papers

The Advantage of Using a File Data Transfer Method in a Plant Design

Michael Fung, Andy Fung, Richard H. Fung, P. K. Fung
Proc. ASME. PVP2014, Volume 3: Design and Analysis, V003T03A021, July 20–24, 2014
Paper No: PVP2014-28044
DOI: https://doi.org/10.1115/PVP2014-28044
View Paper titled, The Advantage of Using a File Data Transfer Method in a Plant Design
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Topics: Plant design, Stress analysis (Engineering), Pipes, Piping design, Structural analysis, Computer software, Design, Modeling, Petrochemicals, Stress
Proceedings Papers

A Flaw Tolerance Concept for Plant Maintenance Using Virtual Fatigue Crack Growth Curve

Masayuki Kamaya, Takao Nakamura
Proc. ASME. PVP2013, Volume 1A: Codes and Standards, V01AT01A028, July 14–18, 2013
Paper No: PVP2013-97851
DOI: https://doi.org/10.1115/PVP2013-97851
View Paper titled, A Flaw Tolerance Concept for Plant Maintenance Using Virtual Fatigue Crack Growth Curve
Click here to open pdf in another window PDF for A Flaw Tolerance Concept for Plant Maintenance Using Virtual Fatigue Crack Growth Curve
Topics: Fatigue cracks, Plant maintenance, Fracture (Materials), ASME Boiler and Pressure Vessel Code, Fatigue life, Maintenance, Plant design, Safety, Design, Fatigue
Proceedings Papers

Development of Limit State Design for Fast Reactor by System Based Code

Daigo Watanabe, Yasuharu Chuman, Tai Asayama, Shigeru Takaya, Hideo Machida, Yoshio Kamishima
Proc. ASME. PVP2013, Volume 1B: Codes and Standards, V01BT01A031, July 14–18, 2013
Paper No: PVP2013-97154
DOI: https://doi.org/10.1115/PVP2013-97154
View Paper titled, Development of Limit State Design for Fast Reactor by System Based Code
Click here to open pdf in another window PDF for Development of Limit State Design for Fast Reactor by System Based Code
Topics: Design, Fast neutron reactors, Stress, Acceptance criteria, Design methodology, Plant design, Reactor vessels
Proceedings Papers

Alternate Requirements for Protection Against Pressurized Thermal Shock (PTS)

Stephen M. Parker, Nathan A. Palm, Xavier Pitoiset
Proc. ASME. PVP2013, Volume 5: High-Pressure Technology; ASME NDE Division; Rudy Scavuzzo Student Paper Symposium, V005T10A002, July 14–18, 2013
Paper No: PVP2013-97577
DOI: https://doi.org/10.1115/PVP2013-97577
View Paper titled, Alternate Requirements for Protection Against Pressurized Thermal Shock (PTS)
Click here to open pdf in another window PDF for Alternate Requirements for Protection Against Pressurized Thermal Shock (PTS)
Topics: Thermal shock, Pressurized water reactors, Embrittlement, Fracture mechanics, In-service inspection, Nuclear power stations, Plant design, Regulations
Proceedings Papers

LBB Under Beyond Design Basis Seismic Loading

Tao Zhang, Frederick W. Brust, Gery Wilkowski, Heqin Xu, Alfredo A. Betervide, Oscar Mazzantini
Proc. ASME. PVP2012, Volume 8: Seismic Engineering, 55-64, July 15–19, 2012
Paper No: PVP2012-78581
DOI: https://doi.org/10.1115/PVP2012-78581
View Paper titled, LBB Under Beyond Design Basis Seismic Loading
Click here to open pdf in another window PDF for LBB Under Beyond Design Basis Seismic Loading
Topics: Design, Fracture (Materials), Nuclear power stations, Pipes, Earthquakes, Heavy water reactors, Leakage, Water, Construction, Dynamic response
Proceedings Papers

Comparison of Plant Life Management Approaches for Long Term Operations

Frank Nuzzo, Ki-Sig Kang
Proc. ASME. PVP2012, Volume 7: Operations, Applications and Components, 61-69, July 15–19, 2012
Paper No: PVP2012-78854
DOI: https://doi.org/10.1115/PVP2012-78854
View Paper titled, Comparison of Plant Life Management Approaches for Long Term Operations
Click here to open pdf in another window PDF for Comparison of Plant Life Management Approaches for Long Term Operations
Topics: Cycles, Design, Education, Fukushima nuclear disaster, Japan, 2011, Licensing, Maintenance, Nuclear power, Nuclear power stations, Plant design, Safety
Proceedings Papers

A Risk-Informed Assessment of ASME Section XI, Appendix E

Ronald Gamble, William Server, Bruce Bishop, Nathan Palm, Carol Heinecke
Proc. ASME. PVP2011, Volume 6: Materials and Fabrication, Parts A and B, 941-954, July 17–21, 2011
Paper No: PVP2011-57201
DOI: https://doi.org/10.1115/PVP2011-57201
View Paper titled, A Risk-Informed Assessment of ASME Section XI, Appendix E
Click here to open pdf in another window PDF for A Risk-Informed Assessment of ASME Section XI, Appendix E
Topics: Risk, Boiling water reactors, Acceptance criteria, ASME Boiler and Pressure Vessel Code, ASME Standards, Heat, Mechanical engineers, Plant design, Reactor vessels, Thermal shock