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Stan T. Rosinski
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Proceedings Papers

Development of High Temperature Semiconductor Strain Gages for Thermal Power Plant Applications

Christopher A. Suprock, Joseph J. Christian, Stan T. Rosinski
Proc. ASME. PVP2018, Volume 7: Operations, Applications, and Components, V007T07A002, July 15–20, 2018
Paper No: PVP2018-84137
DOI: https://doi.org/10.1115/PVP2018-84137
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Topics: High temperature, Semiconductors (Materials), Strain gages, Thermal power stations, Temperature, Energy generation, Engineers, Failure, Gages, Heat
Proceedings Papers

Online Creep-Fatigue Monitoring of Cyclic Operation in a Coal-Fired Power Plant

Stan T. Rosinski, Kent Coleman, Mario Berasi, Curt Carney, Ulrich Woerz, Andres Sanchez, Stefano Sigali, Nicola Rossi
Proc. ASME. PVP2017, Volume 7: Operations, Applications and Components, V007T07A001, July 16–20, 2017
Paper No: PVP2017-65055
DOI: https://doi.org/10.1115/PVP2017-65055
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Topics: Coal, Creep, Fatigue, Power stations, Fatigue damage, Computer software, Damage, Geometry, High temperature, Stress
Proceedings Papers

Application of Master Curve Data for Reactor Vessel Steels

William L. Server, Timothy J. Griesbach, Stan T. Rosinski
Proc. ASME. PVP2003, Application of Fracture Mechanics in Failure Assessment, 99-102, July 20–24, 2003
Paper No: PVP2003-2013
DOI: https://doi.org/10.1115/PVP2003-2013
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Topics: Reactor vessels, Steel, Fracture toughness, Databases, ASME Standards, Brittleness, Forging, Geometry, Phase transition temperature, Pressure vessels
Proceedings Papers

Modeling Swirl Penetration and Thermal Cycling in Un-Isolable Branch Lines of PWR Plants

Jeffrey D. Keller, Alan J. Bilanin, Stan T. Rosinski
Proc. ASME. PVP2003, Aging Management and Component Analysis, 87-94, July 20–24, 2003
Paper No: PVP2003-2156
DOI: https://doi.org/10.1115/PVP2003-2156
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Topics: Modeling, Pressurized water reactors, Pipes, Boundary-value problems, Coolants, Fatigue cracks, Fluids, Industrial research, Model development, Reynolds number
Proceedings Papers

Probabilistic Analysis of 60-Year Environmental Fatigue Effects for Reactor Components

Arthur F. Deardorff, Dilip Dedhia, Stan T. Rosinski, David O. Harris
Proc. ASME. PVP2003, Pressure Vessel and Piping Codes and Standards, 151-160, July 20–24, 2003
Paper No: PVP2003-1779
DOI: https://doi.org/10.1115/PVP2003-1779
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Topics: Fatigue, Damage, Leakage, Probability, Stress, Boiling water reactors, Cycles, Fatigue testing, Fracture (Materials), Fracture mechanics
Proceedings Papers

Consideration of Environmental Fatigue in the ASME Code for Carbon and Low-Alloy Steel Components

Stan T. Rosinski, Arthur F. Deardorff, Robert E. Nickell
Proc. ASME. PVP2003, Pressure Vessel and Piping Codes and Standards, 135-144, July 20–24, 2003
Paper No: PVP2003-1777
DOI: https://doi.org/10.1115/PVP2003-1777
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Topics: Alloys, ASME Standards, Carbon, Fatigue, Steel, Water, Fatigue life, Light water reactors, Engineering design processes, Nuclear industry
Proceedings Papers

Assessment of U.S. Embrittlement Trend Equations Considering the Latest Available Surveillance Data

William L. Server, Randy G. Lott, Stan T. Rosinski
Proc. ASME. PVP2004, Storage Tank Integrity and Materials Evaluation, 19-24, July 25–29, 2004
Paper No: PVP2004-3053
DOI: https://doi.org/10.1115/PVP2004-3053
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Topics: Embrittlement, Surveillance, Boiling water reactors, ASTM International, Databases, Heat, Pressurized water reactors, Thermal shock