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Proceedings Papers

Analysis of Ductile Crack Growth in Pipe Test in STYLE Project

Shengjun Yin, Paul T. Williams, Hilda B. Klasky, B. Richard Bass

Proc. ASME. PVP2012, Volume 6: Materials and Fabrication, Parts A and B, 487-496, July 15–19, 2012

Paper No: PVP2012-78518

DOI: https://doi.org/10.1115/PVP2012-78518

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Topics: Ductile fracture, Pipes, Finite element analysis, Stress, Collapse, Failure, Failure mechanisms, Fracture (Materials), Fracture mechanics, Modeling

Proceedings Papers

Supplemental Stress and Fracture Mechanics Analyses of Pressurized Water Reactor Pressure Vessel Nozzles

Matthew Walter, Shengjun Yin, Gary L. Stevens, Daniel Sommerville, Nathan Palm, Carol Heinecke

Proc. ASME. PVP2012, Volume 3: Design and Analysis, 737-747, July 15–19, 2012

Paper No: PVP2012-78119

DOI: https://doi.org/10.1115/PVP2012-78119

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Topics: Fracture mechanics, Nozzles, Pressure vessels, Pressurized water reactors, Stress, Finite element model, Pressure, Boiling water reactors, Fracture (Materials), Boilers

Proceedings Papers

NESC-VII: Fracture Mechanics Analyses of WPS Experiments on Large-Scale Cruciform Specimen

Shengjun Yin, Paul T. Williams, B. Richard Bass

Proc. ASME. PVP2011, Volume 6: Materials and Fabrication, Parts A and B, 245-254, July 17–21, 2011

Paper No: PVP2011-57112

DOI: https://doi.org/10.1115/PVP2011-57112

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Topics: Fracture mechanics, Stress, Fracture (Materials), Fracture (Process), Reactor vessels, Computers, Numerical analysis, Regulations, Risk, Structural elements (Construction)

Proceedings Papers

ORNL Pre-Test Analyses of a Large-Scale Experiment in STYLE

Paul T. Williams, Shengjun Yin, Hilda B. Klasky, B. Richard Bass

Proc. ASME. PVP2011, Volume 6: Materials and Fabrication, Parts A and B, 283-292, July 17–21, 2011

Paper No: PVP2011-57373

DOI: https://doi.org/10.1115/PVP2011-57373

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Topics: Experimental design, Finite element analysis, Fracture (Materials), Fracture mechanics, Modeling, Nuclear industry, Nuclear reactor coolants, Numerical analysis, Pipes, Pressure

Proceedings Papers

Derivation of the New Pressurized Thermal Shock Screening Criteria

Terry Dickson, Shengjun Yin, Mark Kirk, Hsuing-Wei Chou

Proc. ASME. PVP2011, Volume 1: Codes and Standards, 545-554, July 17–21, 2011

Paper No: PVP2011-57008

DOI: https://doi.org/10.1115/PVP2011-57008

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Topics: Thermal shock, Regulations, Fracture mechanics, Nuclear industry, Risk, Temperature

Proceedings Papers

Verification of New Capabilities of Deterministic Load Module of FAVOR 09.1

Shengjun Yin, Terry L. Dickson, Paul T. Williams, B. Richard Bass

Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 6, Parts A and B, 129-138, July 18–22, 2010

Paper No: PVP2010-25439

DOI: https://doi.org/10.1115/PVP2010-25439

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Topics: Boiling water reactors, Fracture (Materials), Fracture (Process), Heat, Pressure, Pressurized water reactors, Risk, Safety, Software design, Stress

Proceedings Papers

A Generalization of the FAVOR Code to Include BWR Geometries and Heat-Up Transients

Terry Dickson, Shengjun Yin, Paul Williams

Proc. ASME. PVP2009, Volume 7: Operations, Applications and Components, 323-331, July 26–30, 2009

Paper No: PVP2009-77106

DOI: https://doi.org/10.1115/PVP2009-77106

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Topics: Boiling water reactors, Heat, Transients (Dynamics), Pressurized water reactors, Fracture mechanics, Computers, Radiation (Physics), Stress, Tension, Embrittlement

Proceedings Papers

Final Results of an Analytical Round Robin Exercise to Support Constraint Effects

Marc Scibetta, Eberhard Altstadt, Rogelio Herna´ndez Callejas, Bong-Sang Lee, Naoki Miura, Kunio Onizawa, Elena Paffumi, Marta Serrano, Levente Tatar, Shengjun Yin

Proc. ASME. PVP2009, Volume 6: Materials and Fabrication, Parts A and B, 1017-1027, July 26–30, 2009

Paper No: PVP2009-77722

DOI: https://doi.org/10.1115/PVP2009-77722

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Topics: Carbon reinforced plastics, Errors, Finite element analysis, Finite element methods, Fracture (Materials), Fracture toughness, Geometry, Light water reactors, Modeling, Nuclear industry

Proceedings Papers

Accounting for Crack Propagation in a Model to Predict Fracture Toughness in Ferritic Steels

Marjorie A. EricksonKirk, Matthew Wagenhofer, Paul T. Williams, Shengjun Yin

Proc. ASME. PVP2009, Volume 6: Materials and Fabrication, Parts A and B, 1029-1039, July 26–30, 2009

Paper No: PVP2009-77728

DOI: https://doi.org/10.1115/PVP2009-77728

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Topics: Accounting, Crack propagation, Fracture toughness, Steel, Microcracks, Temperature effects, Brittleness, Deformation, Electromagnetic scattering, Failure

Proceedings Papers

Stress Intensity Factor Influence Coefficients for External Surface Flaws in Boiling Water Reactor Pressure Vessels

Shengjun Yin, Terry L. Dickson, Paul T. Williams, B. Richard Bass

Proc. ASME. PVP2009, Volume 3: Design and Analysis, 241-251, July 26–30, 2009

Paper No: PVP2009-77143

DOI: https://doi.org/10.1115/PVP2009-77143

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Topics: Boiling water reactors, Pressure vessels, Stress, Transients (Dynamics), Databases, Fracture mechanics, Heat, Fracture (Materials), Fracture (Process), Nuclear power stations

Proceedings Papers

Applicability of ( K , T -Stress) Methodology to Analyze RPV Under Thermal-Hydraulic Transients

Shengjun Yin, Paul T. Williams, Terry L. Dickson, B. Richard Bass

Proc. ASME. PVP2007, Volume 6: Materials and Fabrication, 167-176, July 22–26, 2007

Paper No: PVP2007-26845

DOI: https://doi.org/10.1115/PVP2007-26845

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Topics: Stress, Transients (Dynamics), Fracture (Materials), Deformation, Emergencies, Numerical analysis, Plasticity, Reactor vessels

Proceedings Papers

Cleavage Fracture Analysis of Cladded Beams With an Embedded Flaw Under Four-Point Bending

Shengjun Yin, Paul T. Williams, B. Richard Bass

Proc. ASME. PVP2008, Volume 6: Materials and Fabrication, Parts A and B, 103-110, July 27–31, 2008

Paper No: PVP2008-61388

DOI: https://doi.org/10.1115/PVP2008-61388

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Topics: Failure, Fracture (Materials), Fracture (Process), Fracture mechanics, Fracture toughness, Hydrostatics, Nuclear research, Probability, Reactor vessels, Shapes

Proceedings Papers

Analysis of Embedded and Surface Flaws in the Beltline of an RPV Subjected to Cyclic Loading Associated With Normal Operational Cool-Down and Heat-Up Transients: A Scoping Study

Shengjun Yin, Terry L. Dickson, Paul T. Williams, B. Richard Bass

Proc. ASME. PVP2008, Volume 6: Materials and Fabrication, Parts A and B, 91-101, July 27–31, 2008

Paper No: PVP2008-61387

DOI: https://doi.org/10.1115/PVP2008-61387

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Topics: Heat, Transients (Dynamics), Cycles, Hardening, Nuclear power stations, Reactor vessels, Service life (Equipment), Thermal shock

Proceedings Papers

Effect of Shallow Flaws and Biaxial Loading on Transition Temperatures Using a Weibull Stress Model

Shengjun Yin, Richard Bass, Paul Williams, Michael Ludwig, Elisabeth Keim

Proc. ASME. PVP2004, Flaw Evaluation, Service Experience, and Materials for Hydrogen Service, 77-84, July 25–29, 2004

Paper No: PVP2004-2547

DOI: https://doi.org/10.1115/PVP2004-2547

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Topics: Phase transition temperature, Stress

Proceedings Papers

Application of a Weibull Stress Model to Predict the Failure of Surface and Embedded Cracks in Large Scale Beams Made of Clad and Unclad RPV Steel

Shengjun Yin, Richard Bass, Paul Williams, Michael Ludwig, Elisabeth Keim

Proc. ASME. PVP2004, Flaw Evaluation, Service Experience, and Materials for Hydrogen Service, 69-76, July 25–29, 2004

Paper No: PVP2004-2546

DOI: https://doi.org/10.1115/PVP2004-2546

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Topics: Failure, Fracture (Materials), Steel, Stress, Cladding systems (Building), Finite element methods, Performance, Phase transition temperature, Probability, Temperature

Journal citation

NARROW

Analysis of Ductile Crack Growth in Pipe Test in STYLE Project

Supplemental Stress and Fracture Mechanics Analyses of Pressurized Water Reactor Pressure Vessel Nozzles

NESC-VII: Fracture Mechanics Analyses of WPS Experiments on Large-Scale Cruciform Specimen

ORNL Pre-Test Analyses of a Large-Scale Experiment in STYLE

Derivation of the New Pressurized Thermal Shock Screening Criteria

Verification of New Capabilities of Deterministic Load Module of FAVOR 09.1

A Generalization of the FAVOR Code to Include BWR Geometries and Heat-Up Transients

Final Results of an Analytical Round Robin Exercise to Support Constraint Effects

Accounting for Crack Propagation in a Model to Predict Fracture Toughness in Ferritic Steels

Stress Intensity Factor Influence Coefficients for External Surface Flaws in Boiling Water Reactor Pressure Vessels

Applicability of ( K , T -Stress) Methodology to Analyze RPV Under Thermal-Hydraulic Transients

Cleavage Fracture Analysis of Cladded Beams With an Embedded Flaw Under Four-Point Bending

Analysis of Embedded and Surface Flaws in the Beltline of an RPV Subjected to Cyclic Loading Associated With Normal Operational Cool-Down and Heat-Up Transients: A Scoping Study

Effect of Shallow Flaws and Biaxial Loading on Transition Temperatures Using a Weibull Stress Model

Application of a Weibull Stress Model to Predict the Failure of Surface and Embedded Cracks in Large Scale Beams Made of Clad and Unclad RPV Steel

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