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Proceedings Papers

Effect of Coolant Water Temperature of ECCS on Failure Probability of RPV

Jinya Katsuyama, Koichi Masaki, Kai Lu, Tadashi Watanabe, Yinsheng Li
Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A059, July 14–19, 2019
Paper No: PVP2019-93967
DOI: https://doi.org/10.1115/PVP2019-93967
View Paper titled, Effect of Coolant Water Temperature of ECCS on Failure Probability of RPV
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Topics: Coolants, Emergency core cooling systems, Failure, Fracture mechanics, Probability, Thermal shock, Water temperature, Temperature, Pressure, Pressurized water reactors
Proceedings Papers

Use of Engineered Materials to Reduce Both Strainer Head Loss and Fiber Bypass for Emergency Core Cooling Systems

Alan J. Bilanin, Andrew E. Kaufman, Warren J. Bilanin
Proc. ASME. PVP2019, Volume 7: Operations, Applications, and Components, V007T07A012, July 14–19, 2019
Paper No: PVP2019-93681
DOI: https://doi.org/10.1115/PVP2019-93681
View Paper titled, Use of Engineered Materials to Reduce Both Strainer Head Loss and Fiber Bypass for Emergency Core Cooling Systems
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Topics: Emergency core cooling systems, Fibers
Proceedings Papers

Optimizing Maintenance Strategy of a Reactor Pressure Vessel Using 3D-CFD and FEM Based Probabilistic Pressurized Thermal Shock Analysis

Xiaoyong Ruan, Toshiki Nakasuji, Kazunori Morishita
Proc. ASME. PVP2017, Volume 5: High-Pressure Technology; ASME Nondestructive Evaluation, Diagnosis and Prognosis Division (NDPD); SPC Track for Senate, V005T11A019, July 16–20, 2017
Paper No: PVP2017-65072
DOI: https://doi.org/10.1115/PVP2017-65072
View Paper titled, Optimizing Maintenance Strategy of a Reactor Pressure Vessel Using 3D-CFD and FEM Based Probabilistic Pressurized Thermal Shock Analysis
Click here to open pdf in another window PDF for Optimizing Maintenance Strategy of a Reactor Pressure Vessel Using 3D-CFD and FEM Based Probabilistic Pressurized Thermal Shock Analysis
Topics: Computational fluid dynamics, Finite element methods, Maintenance, Reactor vessels, Thermal shock, Fracture (Materials), Coolants, Emergency core cooling systems, Probability, Safety
Proceedings Papers

Recapturing Net Positive Suction Head Margins in Boiling Water Reactor Emergency Core Cooling Systems

Alan J. Bilanin, Andrew E. Kaufman, Warren J. Bilanin
Proc. ASME. PVP2017, Volume 7: Operations, Applications and Components, V007T07A004, July 16–20, 2017
Paper No: PVP2017-66141
DOI: https://doi.org/10.1115/PVP2017-66141
View Paper titled, Recapturing Net Positive Suction Head Margins in Boiling Water Reactor Emergency Core Cooling Systems
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Topics: Boiling water reactors, Emergency core cooling systems, Suction, Cooling, Water, Accidents, Containment, Coolants, Cooling systems, Insulation
Proceedings Papers

Emergency Core Cooling System Sump Strainer Fibre Bypass Testing and Measurement

Qingwu Cheng, Harry Adams, Metin Yetisir
Proc. ASME. PVP2016, Volume 7: Operations, Applications and Components, V007T07A004, July 17–21, 2016
Paper No: PVP2016-63855
DOI: https://doi.org/10.1115/PVP2016-63855
View Paper titled, Emergency Core Cooling System Sump Strainer Fibre Bypass Testing and Measurement
Click here to open pdf in another window PDF for Emergency Core Cooling System Sump Strainer Fibre Bypass Testing and Measurement
Topics: Emergency core cooling systems, Fibers, Testing, Filtration, Fuels, Nuclear power stations, Regulations, Accidents, Coolants, Cooling
Proceedings Papers

Prediction of Margins in the TBS Seismic Considerations Analysis for Circumferential Surface-Cracked Piping Under Beyond Design Basis Seismic Loading

Mohammed Uddin, Frederick Brust, Gery Wilkowski, Tao Zhang, A. A. Betervide, O. Mazzantini, Ricardo A. Fernandez
Proc. ASME. PVP2014, Volume 8: Seismic Engineering, V008T08A025, July 20–24, 2014
Paper No: PVP2014-28819
DOI: https://doi.org/10.1115/PVP2014-28819
View Paper titled, Prediction of Margins in the TBS Seismic Considerations Analysis for Circumferential Surface-Cracked Piping Under Beyond Design Basis Seismic Loading
Click here to open pdf in another window PDF for Prediction of Margins in the TBS Seismic Considerations Analysis for Circumferential Surface-Cracked Piping Under Beyond Design Basis Seismic Loading
Topics: Design, Pipes, Fracture (Materials), ASME Standards, Earthquake risk, Earthquakes, Finite element model, Probability, Stress, Surface cracks
Proceedings Papers

Benchmarking xLPR Version 1.0 With the PRO-LOCA Version 3.0 Code

Robert Kurth, Elizabeth Kurth, Bruce Young, Andrew Cox, Rick Olson, Paul Scott, Dave Rudland, Raj Iyengar, Craig Harrington
Proc. ASME. PVP2012, Volume 6: Materials and Fabrication, Parts A and B, 723-729, July 15–19, 2012
Paper No: PVP2012-78170
DOI: https://doi.org/10.1115/PVP2012-78170
View Paper titled, Benchmarking xLPR Version 1.0 With the PRO-LOCA Version 3.0 Code
Click here to open pdf in another window PDF for Benchmarking xLPR Version 1.0 With the PRO-LOCA Version 3.0 Code
Topics: Design, Electricity (Physics), Emergency core cooling systems, Engineering mechanics, Fracture (Materials), Fracture mechanics, Leadership, Leakage, Nuclear industry, Pipes
Proceedings Papers

Robust LBB Analyses for Atucha II Nuclear Plant

G. Wilkowski, B. Brust, T. Zhang, G. Hattery, S. Kalyanam, D.-J. Shim, E. Kurth, Y. Hioe, M. Uddin, J. J. Johnson, O. R. Maslenikov, A. Gu¨rpinar, A. P. Asfura, B. Sumodobila, A. A. Betervide, O. Mazzantini
Proc. ASME. PVP2011, Volume 1: Codes and Standards, 107-120, July 17–21, 2011
Paper No: PVP2011-57939
DOI: https://doi.org/10.1115/PVP2011-57939
View Paper titled, Robust LBB Analyses for Atucha II Nuclear Plant
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Topics: Nuclear power stations, Stress, Design, Fracture (Materials), Emergency core cooling systems, Leakage, Pipes, Construction, Displacement, Residual stresses
Proceedings Papers

Use of LBB Methodology to Support the Transition Break Size Concept

James E. Nestell, David W. Rackiewicz
Proc. ASME. PVP2011, Volume 1: Codes and Standards, 47-56, July 17–21, 2011
Paper No: PVP2011-57680
DOI: https://doi.org/10.1115/PVP2011-57680
View Paper titled, Use of LBB Methodology to Support the Transition Break Size Concept
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Topics: Accidents, Coolants, Cooling, Defense industry, Design, Emergency core cooling systems, Failure, Leak-before-break, Nuclear power stations, Nuclear reactor coolants
Proceedings Papers

Progress in RI ISI Applications for WWER 440 and WWER 1000 Type Piping Systems

Ladislav Horacek
Proc. ASME. PVP2009, Volume 5: High Pressure Technology; Nondestructive Evaluation Division; Student Paper Competition, 271-276, July 26–30, 2009
Paper No: PVP2009-77165
DOI: https://doi.org/10.1115/PVP2009-77165
View Paper titled, Progress in RI ISI Applications for WWER 440 and WWER 1000 Type Piping Systems
Click here to open pdf in another window PDF for Progress in RI ISI Applications for WWER 440 and WWER 1000 Type Piping Systems
Topics: Piping systems, Risk-informed in-service inspection, Welded joints, Nuclear power stations, Pipes, Inspection, Containment, Emergency core cooling systems, Fatigue, Risk
Proceedings Papers

An Integrated Approach for Monitoring Gas Accumulation in Safety Related Systems

L. Ike Ezekoye, Ryan D. Griffin, William M. Turkowski, Gregory R. Williams
Proc. ASME. PVP2009, Volume 7: Operations, Applications and Components, 53-60, July 26–30, 2009
Paper No: PVP2009-77957
DOI: https://doi.org/10.1115/PVP2009-77957
View Paper titled, An Integrated Approach for Monitoring Gas Accumulation in Safety Related Systems
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Topics: Safety, Pumps, Design, Pipes, Emergency core cooling systems, Gases, Containment, Damage, Flow (Dynamics), Heat
Proceedings Papers

PTS Evaluation for Czech Nuclear Power Plants of WWER Type

Vladislav Pistora, Pavel Kral
Proc. ASME. PVP2009, Volume 7: Operations, Applications and Components, 217-224, July 26–30, 2009
Paper No: PVP2009-77405
DOI: https://doi.org/10.1115/PVP2009-77405
View Paper titled, PTS Evaluation for Czech Nuclear Power Plants of WWER Type
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Topics: Nuclear power stations, Finite element methods, Fracture (Materials), Stress, Emergency core cooling systems, Temperature, Brittleness, Circuits, Computation, Computers
Proceedings Papers

Development of Component Specific Ageing Management Programmes for Mechanical Components at the NPP Paks

A´gnes Ja´nosine´ Bi´ro´, Sa´ndor Ra´tkai, Ma´rton Osztheimer, Katalin Baumann-ne´ Tanits, Sa´ndor Baranya
Proc. ASME. PVP2009, Volume 7: Operations, Applications and Components, 393-402, July 26–30, 2009
Paper No: PVP2009-77504
DOI: https://doi.org/10.1115/PVP2009-77504
View Paper titled, Development of Component Specific Ageing Management Programmes for Mechanical Components at the NPP Paks
Click here to open pdf in another window PDF for Development of Component Specific Ageing Management Programmes for Mechanical Components at the NPP Paks
Topics: Acceptance criteria, Boilers, Coolants, Corrective actions, Corrosion, Damage, Emergencies, Emergency core cooling systems, Erosion, Fasteners
Proceedings Papers

An Application of Computational Fluid Dynamics (CFD) Code to the Design of a Multi-Stage Breakdown Orifice in Support of GSI-191 Evaluations

J. C. Adams, L. I. Ezekoye, S. M. Smith, S. R. Swantner
Proc. ASME. PVP2007, Volume 7: Operations, Applications and Components, 217-222, July 22–26, 2007
Paper No: PVP2007-26208
DOI: https://doi.org/10.1115/PVP2007-26208
View Paper titled, An Application of Computational Fluid Dynamics (CFD) Code to the Design of a Multi-Stage Breakdown Orifice in Support of GSI-191 Evaluations
Click here to open pdf in another window PDF for An Application of Computational Fluid Dynamics (CFD) Code to the Design of a Multi-Stage Breakdown Orifice in Support of GSI-191 Evaluations
Topics: Computational fluid dynamics, Design, Valves, Emergency core cooling systems, Flow (Dynamics), Pressure drop, Pressurized water reactors, Emergencies, Wear, Accidents
Proceedings Papers

Revised LOCA Frequency Estimates From an Expert Elicitation Process

Paul M. Scott, Robert Lee Tregoning, Lee Richard Abramson
Proc. ASME. PVP2008, Volume 6: Materials and Fabrication, Parts A and B, 1417-1424, July 27–31, 2008
Paper No: PVP2008-61562
DOI: https://doi.org/10.1115/PVP2008-61562
View Paper titled, Revised LOCA Frequency Estimates From an Expert Elicitation Process
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Topics: Accidents, Coolants, Design, Emergency core cooling systems, Fracture mechanics, Nuclear power stations, Piping systems, Plant design, Risk, Sensitivity analysis
Proceedings Papers

Brittle Fracture Safety Analysis of German RPVs Based on Advanced Thermal Hydraulic Analysis

Elisabeth Keim, Roland Hertlein, Ulf Ilg, Gu¨nter Ko¨nig, Norbert Schlu¨ter, Martin Widera
Proc. ASME. PVP2008, Volume 6: Materials and Fabrication, Parts A and B, 679-686, July 27–31, 2008
Paper No: PVP2008-61188
DOI: https://doi.org/10.1115/PVP2008-61188
View Paper titled, Brittle Fracture Safety Analysis of German RPVs Based on Advanced Thermal Hydraulic Analysis
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Topics: Brittle fracture, Safety, Leakage, Nozzles, Pressurized water reactors, Accidents, Coolants, Design, Flanges, Stress
Proceedings Papers

An Evaluation of Post-LOCA Debris on Multi-Stage Safety-Related Pumps in PWR ECCS in Support of Generic Safety Issue 191 Closure

L. Ike Ezekoye, Rolv Hundal, Paul V. Pyle
Proc. ASME. PVP2008, Volume 7: Operations, Applications and Components, 323-328, July 27–31, 2008
Paper No: PVP2008-61766
DOI: https://doi.org/10.1115/PVP2008-61766
View Paper titled, An Evaluation of Post-LOCA Debris on Multi-Stage Safety-Related Pumps in PWR ECCS in Support of Generic Safety Issue 191 Closure
Click here to open pdf in another window PDF for An Evaluation of Post-LOCA Debris on Multi-Stage Safety-Related Pumps in PWR ECCS in Support of Generic Safety Issue 191 Closure
Topics: Emergency core cooling systems, Pressurized water reactors, Pumps, Safety, Wear, Accidents, Containment, Coolants, Cooling, Containment buildings
Proceedings Papers

Ways for Extending the Reactor Pressure Vessel Lifetime

Milan Brumovsky
Proc. ASME. PVP2008, Volume 7: Operations, Applications and Components, 129-135, July 27–31, 2008
Paper No: PVP2008-61479
DOI: https://doi.org/10.1115/PVP2008-61479
View Paper titled, Ways for Extending the Reactor Pressure Vessel Lifetime
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Topics: Reactor vessels, Vessels, Annealing, Design, Economics , Emergency core cooling systems, Fracture mechanics, Leakage, Manufacturing technology, Nuclear power stations
Proceedings Papers

Seismic Considerations for the Transition Break Size: An Overview of the Methodology

G. Wilkowski, H. Xu, P. Krishnaswamy, N. Chokshi, S. Shaukat, A. Hiser, G. DeGrassi, J. J. Johnson, R. Olson
Proc. ASME. PVP2006-ICPVT-11, Volume 6: Materials and Fabrication, 103-117, July 23–27, 2006
Paper No: PVP2006-ICPVT-11-93994
DOI: https://doi.org/10.1115/PVP2006-ICPVT-11-93994
View Paper titled, Seismic Considerations for the Transition Break Size: An Overview of the Methodology
Click here to open pdf in another window PDF for Seismic Considerations for the Transition Break Size: An Overview of the Methodology
Topics: Accidents, Coolants, Emergency core cooling systems, Regulations, Risk
Proceedings Papers

Buckling of Externally Pressurised Prolate Ellipsoidal Domes

P. Smith, J. Blachut
Proc. ASME. PVP2006-ICPVT-11, Volume 5: High Pressure Technology, Nondestructive Evaluation, Pipeline Systems, Student Paper Competition, 329-337, July 23–27, 2006
Paper No: PVP2006-ICPVT-11-93227
DOI: https://doi.org/10.1115/PVP2006-ICPVT-11-93227
View Paper titled, Buckling of Externally Pressurised Prolate Ellipsoidal Domes
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Topics: Buckling, Domes (Structural elements), Boilers, Boundary-value problems, Design, Emergency core cooling systems, External pressure, Pressure vessels, Shapes, Shells