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Proceedings Papers

Proceedings Volume Cover
ASME 2009 Pressure Vessels and Piping Conference
July 26–30, 2009
Prague, Czech Republic
Conference Sponsors:
  • Pressure Vessels and Piping
ISBN:
978-0-7918-4370-3
Volume 7: Operations, Applications and Components

Operations, Applications, and Components

Safety, Reliability and Risk Assessment

Effects of Post Weld Heat Treatment Residual Stress on the Creep of Elbow Welded Joint
Changyu Zhou, Guodong Zhang
PVP 2009; 3-8https://doi.org/10.1115/PVP2009-77215
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Topics: Creep , Heat treating (Metalworking) , Stress , Welded joints , Pressure , Welding , High temperature , Boiler tubes , Finite element analysis , Design
Generating Confidence in Inspection Results
R. V. Booler, W. L. Daniels, J. P. Taggart
PVP 2009; 9-13https://doi.org/10.1115/PVP2009-78052
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Topics: Inspection , Nondestructive evaluation , Safety , Engineering disciplines , Acceptance criteria , Life extension , Nuclear industry , Probability , Risk-based inspection , Uncertainty
Tearing Resistance Properties of Stainless Steel Orbital TIG Narrow Gap Welds of Primary Piping in PWR Plants
Pascal Ould, Pierre Joly, Sylvain Pillot
PVP 2009; 15-23https://doi.org/10.1115/PVP2009-78077
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Topics: Pipes , Pressurized water reactors , Stainless steel , Welded joints , Coolants , Butt welding , Electrodes , Mechanical properties , Metals , Safety
Reliability of Onsite Emergency Power for the New Generation and Advanced Nuclear Power Plants
Mansoor H. Sanwarwalla
PVP 2009; 25-29https://doi.org/10.1115/PVP2009-78127
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Topics: Emergency power , Nuclear power stations , Reliability , Design , Batteries , Boiling water reactors , Diesel , Energy generation , High temperature , Maintenance

Monitoring, Diagnostics and Inspection

Extending the Internal Examination Intervals for Pressure Vessels Using an RBI Approach
Philippa Moore, John Wintle
PVP 2009; 33-40https://doi.org/10.1115/PVP2009-77196
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Topics: Containment , Environmental health and safety , Failure , Hazards , Health and safety , Inspection , Petrochemicals , Pressure equipment , Pressure vessels , Risk
Dynamic Response of the WWER 1000/320 Reactor on the Pressure Pulsations Generated by Main Circulation Pumps
Ladislav Pecinka, Petr Stulik, Vladimir Zeman
PVP 2009; 41-44https://doi.org/10.1115/PVP2009-77304
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Topics: Dynamic response , Pressure , Pumps , Blades , Boundary layers , Computer simulation , Pressurized water reactors , Rotors , Sound pressure , Turbulence
Estimating ASME Section III and VIII Heat Exchanger Nozzle Loads
L. Ike Ezekoye, Colin Arnold
PVP 2009; 45-52https://doi.org/10.1115/PVP2009-77829
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Topics: Heat exchangers , Nozzles , Stress , Design , Acceptance criteria , Geometry , Heat , Materials properties , Pipes , Power stations
An Integrated Approach for Monitoring Gas Accumulation in Safety Related Systems
L. Ike Ezekoye, Ryan D. Griffin, William M. Turkowski, Gregory R. Williams
PVP 2009; 53-60https://doi.org/10.1115/PVP2009-77957
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Topics: Safety , Pumps , Design , Pipes , Emergency core cooling systems , Gases , Containment , Damage , Flow (Dynamics) , Heat

Toxic Substances: Storage and Transportation

Radiation Heat Transfer Environment in Fire and Furnace Tests of Radioactive Materials Packages
Allen C. Smith
PVP 2009; 63-71https://doi.org/10.1115/PVP2009-77017
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Topics: Fire , Furnaces , Heat transfer , Radiation (Physics) , Radioactive substances , Emissivity , Fuels , Temperature , Accidents , Flames
Thermal Analysis of Drum Type Radioactive Material (RAM) Packaging Arrays in Storage
Narendra K. Gupta
PVP 2009; 73-79https://doi.org/10.1115/PVP2009-77045
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Topics: Packaging , Radioactive substances , Storage , Thermal analysis , Containment vessels , Cushioning materials , Design , Heat , Leakage , Regulations
Security in the Transport of Radioactive Materials
Ronald B. Pope, Richard R. Rawl
PVP 2009; 81-89https://doi.org/10.1115/PVP2009-77089
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Topics: Radioactive substances , Security , Nuclear power , Safety , Training programs , Transportation systems
Strain-Based Acceptance Criteria for Energy-Limited Events
Spencer D. Snow, Dana K. Morton, Edward L. Pleins, Robert Keating
PVP 2009; 91-96https://doi.org/10.1115/PVP2009-77122
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Topics: Acceptance criteria , Design , Stress , Boilers , Design methodology , Displacement , Failure , Mechanical engineers , Pressure vessels , Radioactive substances
Packaging and Transportation of Neptunium Oxide
Robert W. Watkins, Stephen J. Hensel, Jeffrey M. Jordan
PVP 2009; 97-99https://doi.org/10.1115/PVP2009-77200
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Topics: Packaging , Transportation systems , Containers , Rivers , Safety
Burn Behavior of a Polyurethane Foam Impact Limiter
Jie Li, Shiu-Wing Tam, Yung Y. Liu
PVP 2009; 101-108https://doi.org/10.1115/PVP2009-77261
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Topics: Cushioning materials , Urethane foam , Temperature , Flames , Combustion , Containment , Fuels , Gases , Pyrolysis , Design
A Radiofrequency Identification (RFID) Temperature-Monitoring System for Extended Maintenance of Nuclear Materials Packaging
Kun Chen, Hanchung Tsai, Bud Fabian, Yung Liu, James Shuler
PVP 2009; 109-115https://doi.org/10.1115/PVP2009-77265
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Topics: Maintenance , Packaging , Temperature , Seals , Computer software , Containment , Leakage , Transportation systems , Databases , Heat
Operational Readiness of the ES-3100 Type B Shipping Container for Fissile Materials
Jeffrey G. Arbital, Kenneth E. Sanders
PVP 2009; 117-124https://doi.org/10.1115/PVP2009-77416
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Topics: Containers , Licensing , Radioactive substances , Transportation systems
An Analytical Method of Determining Damage Initiation for Potential Use in Establishing Strain-Based Failure Criteria
Tsu-te Wu
PVP 2009; 127-136https://doi.org/10.1115/PVP2009-77435
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Topics: Damage , Failure , Stress , Ductile fracture , Shear (Mechanics) , Computer simulation , Displacement , Fracture (Materials) , Fracture (Process) , Load bearing capacity
Dynamic Analysis of Shipping Cask Subjected to Sequential Bolt Preload and Impact Loads
Tsu-te Wu
PVP 2009; 137-144https://doi.org/10.1115/PVP2009-77438
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Topics: Dynamic analysis , Stress , Dynamic response , Finite element analysis , Structural response analysis
Severe Transportation Accidents: Impacts of Severe Fires on Radioactive Material Transportation
Christopher S. Bajwa, Earl P. Easton, Darrell S. Dunn
PVP 2009; 145-158https://doi.org/10.1115/PVP2009-77790
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Topics: Accidents , Fire , Radioactive substances , Transportation systems , Overpasses , Collapse , Flames , Gasoline , Spent nuclear fuels , Structural steel
Potential Effects of Historic Rail Accidents on the Integrity of Spent Nuclear Fuel Transportation Packages
Christopher S. Bajwa, Earl P. Easton
PVP 2009; 159-165https://doi.org/10.1115/PVP2009-77811
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Topics: Accidents , Rails , Spent nuclear fuels , Transport packages , Fire , Hazardous substances , Radioactive substances , Regulations

Operations and Maintenance of Pressure Vessels, Heat Exchangers, and Structures

Reference Stresses for Cold-Tube-Bends Including Thickness Variation and Ovality Using Three-Dimensional Finite Element Method
Khosrow Zarrabi, Felix Kumiadi Kwok
PVP 2009; 169-174https://doi.org/10.1115/PVP2009-77004
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Topics: Collapse , Finite element methods , Stress
Confirmation of Validity of Hot Tapping Welding
Yasushi Ogayu
PVP 2009; 175-179https://doi.org/10.1115/PVP2009-77072
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Topics: Welding , Pipes , Thermal analysis , Base metals , Pressure , Temperature , Computer simulation , Cooling , Finite element analysis , Heat
Loads Applied to Clogged Steam Generators Internal Structures
Olivier Brunin, Geoffrey Deotto
PVP 2009; 181-190https://doi.org/10.1115/PVP2009-77140
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Topics: Boilers , Stress , Flow (Dynamics) , Cooling , Heat transfer , Mechanical behavior , Modeling , Oscillations , Risk , Safety
Sloshing Characteristics of Single Deck Floating Roofs in Aboveground Storage Tanks: Natural Periods and Vibration Modes
Shoichi Yoshida, Kazuyoshi Sekine, Katsuki Iwata
PVP 2009; 191-199https://doi.org/10.1115/PVP2009-77187
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Topics: Roofs , Sloshing , Storage tanks , Vibration , Fluids , Damage , Design , Earthquakes , Engineers , Evaporation
Buckling Characteristics of Floating Roof Pontoons in Aboveground Storage Tanks Subjected to Both Compressive and Bending Load
Shoichi Yoshida
PVP 2009; 201-210https://doi.org/10.1115/PVP2009-77227
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Topics: Buckling , Roofs , Storage tanks , Stress , Failure , Sloshing , Bifurcation , Buoyancy , Damage , Earthquakes
Improvements of the Containment Measuring System
Jiri Zdarek, Jan Bulak, Petr Vomacka, Milan Brumovsky
PVP 2009; 211-215https://doi.org/10.1115/PVP2009-77400
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Topics: Containment , Stress , Tendons , Nuclear power stations , Computation , Concretes , Emergencies , Expert systems , In-service inspection , Modeling
PTS Evaluation for Czech Nuclear Power Plants of WWER Type
Vladislav Pistora, Pavel Kral
PVP 2009; 217-224https://doi.org/10.1115/PVP2009-77405
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Topics: Nuclear power stations , Finite element methods , Fracture (Materials) , Stress , Emergency core cooling systems , Temperature , Brittleness , Circuits , Computation , Computers
Cracking in Welds of Heavy-Wall Stainless Steel and Nickel Alloy Piping During Fabrication
Tomoaki Kiso, Kunio Ishii, Ichiro Seshimo
PVP 2009; 225-232https://doi.org/10.1115/PVP2009-77554
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Topics: Cracking (Materials) , Fracture (Process) , Manufacturing , Nickel alloys , Pipes , Stainless steel , Welded joints , Heat treating (Metalworking) , Stress , Alloys
Experiences With Controlled Deposition Welding and Fitness for Service in Coke Drums
Jorge A. Penso, M. Victor Li
PVP 2009; 233-241https://doi.org/10.1115/PVP2009-77853
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Topics: Coke , Fitness-for-service , Welding , Charge density waves , Maintenance , Base metals , Computer simulation , Fatigue , Heat , Heat treating (Metalworking)
Effects of Cladding on Reactor Pressure Vessel Integrity Based on the Revised PTS Rule (10 CFR 50.61)
Vikram Marthandam, Timothy J. Griesbach, Jack Spanner
PVP 2009; 243-249https://doi.org/10.1115/PVP2009-78088
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Topics: Cladding systems (Building) , Reactor vessels , Density , Nondestructive evaluation , ASME Standards , Cracking (Materials) , Fracture (Process) , Inspection , Thermal shock , Transients (Dynamics)

Piping and Supports

Transient Flow Analysis of Spring Loaded Pressure Safety Valve
Xue Guan Song, Seong Gul Kim, Lin Wang, Young Chul Park
PVP 2009; 253-258https://doi.org/10.1115/PVP2009-77043
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Topics: Pressure , Safety , Springs , Unsteady flow , Valves , Disks , Computational fluid dynamics , Fluids , Geometry , Design
Buckling Analysis of Plastic Pipe Reinforced by Cross-Winding Steel Wire Under Bending
Xiang Li, Jinyang Zheng, Fengjian Shi, Yongquan Qin, Ping Xu
PVP 2009; 259-268https://doi.org/10.1115/PVP2009-77532
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Topics: Buckling , Composite materials , Finite element analysis , Plastic pipes , Steel , Winding (process) , Wire
Experimental Measurement of the Permeability of Die-Formed Exfoliated Graphite Compression Packings
Didier Lasseux, Pascal Jolly, Yves Jannot, Emmanuel Sauger, Benoit Omnes
PVP 2009; 269-278https://doi.org/10.1115/PVP2009-77659
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Topics: Compression , Graphite , Packings (Cushioning) , Permeability , Pressure , Anisotropy , Gas flow , Leakage , Manufacturing , Nitrogen
Method for Predicting Mixing Tee Thermal Fatigue in Carbon Steel Based on Austenitic Stainless Steel Operating Experience
Robert O. McGill, David O. Harris, Ken Wolfe
PVP 2009; 279-286https://doi.org/10.1115/PVP2009-77975
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Topics: Carbon steel , Fatigue , Stainless steel , Leakage , Pipes , Boiling water reactors , Fatigue cracks , Fluids , Heat , Piping systems
GRE Pipeline Installation Procedures: A Field Case Study
A. Khalaf, Y. Al-Tartoor, A. C. Seibi, A. Karrech
PVP 2009; 287-295https://doi.org/10.1115/PVP2009-78017
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Topics: Pipelines , Pipes , Failure , Pipe sizes , Stress , Cantilever beams , Deflection , Deformation , Epoxy adhesives , Epoxy resins

Aging Management and Life Extension

Reporting on Plant Condition: The Big Picture
Quentin D. Gryl, Robert H. Frith
PVP 2009; 299-309https://doi.org/10.1115/PVP2009-77012
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Topics: Design , Hazards , Industrial plants , Maintenance , Performance
Managing Change in a High Growth Environment: Reference to Bahrain/Arabian Gulf
Aby Thomas
PVP 2009; 311-321https://doi.org/10.1115/PVP2009-77036
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Topics: American Petroleum Institute , Construction , Gas industry , Natural gas fields , Petroleum , Piping systems , Safety
A Generalization of the FAVOR Code to Include BWR Geometries and Heat-Up Transients
Terry Dickson, Shengjun Yin, Paul Williams
PVP 2009; 323-331https://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
The Sensitivity of Risk-Informed Reactor Structural Integrity Analysis Results to Various Interpretations of Warm Pre-Stress
Mark T. EricksonKirk, Terry L. Dickson
PVP 2009; 333-339https://doi.org/10.1115/PVP2009-77127
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Topics: Risk , Stress , Transients (Dynamics) , Fracture (Materials) , Fracture (Process) , Accidents , Failure , Modeling , Temperature , Vessels
Preparation of Long Term Operation in Dukovany NPP, Czech Republic
Robert Krivanek
PVP 2009; 341-346https://doi.org/10.1115/PVP2009-77231
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Topics: Nuclear power stations , Risk analysis , Design , Safety
Implementation of PLIM and AMPs in Czech NPPs
Robert Krivanek
PVP 2009; 347-353https://doi.org/10.1115/PVP2009-77233
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Topics: Amperes , Nuclear power stations , Power stations
Nuclear PWR Plants Mitigation of Reactor Coolant System Areas to Consider Plants Aging Management and/or Life Extension
Re´mi Thevenet
PVP 2009; 355-374https://doi.org/10.1115/PVP2009-77354
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Topics: Life extension , Nuclear reactor coolants , Pressurized water reactors , Fracture (Materials) , Risk , Water , Maintenance , Nozzles , Reactor vessels , Alloys
Remaining Lifetime Evaluation of High Temperature Components of Power Plant Steam Boilers: Case Studies
Vaclav Mentl, Va´clav Lisˇka, Jaroslav Koc, Michal Chocholousˇek
PVP 2009; 375-381https://doi.org/10.1115/PVP2009-77381
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Topics: Boilers , High temperature , Power stations , Safety , Stress , Temperature , Inspection , Creep , Failure , Fatigue
CFD-Tools for Assessment of the Reactor Pressure Vessel Integrity in Pressure Thermal Shock Conditions: Thermal-Hydraulic Methods and Main Industrial Results on the French 900 MWe PWR RPV
A. Martin, F. Lestang, S. Bellet, D. Guichard, C. Vit, S. Cornille, A. Barbier, F. Huvelin
PVP 2009; 383-391https://doi.org/10.1115/PVP2009-77390
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Topics: Computational fluid dynamics , Fracture mechanics , Pressure , Pressurized water reactors , Reactor vessels , Thermal shock
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
PVP 2009; 393-402https://doi.org/10.1115/PVP2009-77504
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Topics: Acceptance criteria , Boilers , Coolants , Corrective actions , Corrosion , Damage , Emergencies , Emergency core cooling systems , Erosion , Fasteners
ARCMAC Optical Strain Measurement for Creep Monitoring: Recent Improvements in Accuracy and Resolution
Andy Morris, Iain Palmer, Chris Maharaj, Amit Puri, John Dear
PVP 2009; 403-410https://doi.org/10.1115/PVP2009-77511
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Topics: Creep , Resolution (Optics) , Strain measurement , Pipes , Steam , Errors , Gages , Strain gages , Blades , Design
Extension of Operational Life-Time of WWER-440/213 Type Units at Paks Nuclear Power Plant
Tama´s Ja´nos Katona, Sa´ndor Ra´tkai, A´gnes Ja´nosine´ Bi´ro´
PVP 2009; 411-418https://doi.org/10.1115/PVP2009-77513
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Topics: Nuclear power stations , Design , Licensing , Safety , Engineering systems and industry applications , Thermal energy
Degradation Mechanisms Control of Mechanical Components During Operation
Lubomir Junek, Jaroslav Bartonicek, Milan Vrana
PVP 2009; 419-425https://doi.org/10.1115/PVP2009-77655
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Topics: Corrosion , Damage , Design , Dimensions , Dynamic testing (Materials) , Emergencies , Errors , Failure , Geometry , Inspection
Microstructure and Mechanical Properties of G17CrMoV5 – 10 Cast Steel After Regenerative Heat Treatment
Grzegorz Golan´ski
PVP 2009; 427-434https://doi.org/10.1115/PVP2009-77710
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Topics: Heat treating (Metalworking) , Mechanical properties , Steel , Temperature , Brittleness , Steam turbines , Tensile strength , Yield strength
Integrity and Life Assessment of Cast Duplex Stainless Steel Elbows Used in the Primary Loops of PWRs
N. Ligneau, C. Page`s, M. Akamatsu, C. Pokor, V. Calonne-Chatelee
PVP 2009; 435-443https://doi.org/10.1115/PVP2009-77731
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Topics: Pressurized water reactors , Stainless steel , Fracture toughness , Manufacturing , Casting , Cavities , Crack propagation , Databases , Embrittlement , Engineering instruments
Statical Computation of the Main Building
Istva´n Mo´ga
PVP 2009; 445-452https://doi.org/10.1115/PVP2009-77735
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Topics: Computation , Regulations
Assessment of the Fatigue Life of a PWR Surge Line Including the Effect of Coolant Environment
Gu¨nter Ko¨nig, Jaroslav Bartonicek, Horst Rothenho¨fer
PVP 2009; 453-460https://doi.org/10.1115/PVP2009-77739
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Topics: Coolants , Fatigue life , Pressurized water reactors , Surges , Design , Failure , Fatigue , Boundary-value problems , Corrosion , Damage
Materials Aging Degradation of Reactor Vessel Internals: Part III—Structural Evaluation and Local Finite Element Models
Matthew D. Snyder, Tama´s R. Liszkai, Anne Demma
PVP 2009; 461-468https://doi.org/10.1115/PVP2009-77784
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Topics: Finite element model , Reactor vessels , Manufacturing , Computational fluid dynamics , Constitutive equations , Failure mechanisms , Pressurized water reactors , Radiation (Physics) , Stress , Structural analysis
Materials Aging Degradation of Reactor Vessel Internals: Part II—Structural Evaluation and Global Finite Element Models
Tama´s R. Liszkai, Matthew Snyder, Anne Demma
PVP 2009; 469-479https://doi.org/10.1115/PVP2009-77786
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Topics: Finite element model , Reactor vessels , Manufacturing , Computational fluid dynamics , Pressurized water reactors , Constitutive equations , Failure mechanisms , Radiation (Physics) , Stress , Structural analysis
On the Role of Fracture Mechanics Assessment Within the Integrity Concept
Guenter Koenig, Jaroslav Bartonicek, Friedrich Schoeckle
PVP 2009; 481-488https://doi.org/10.1115/PVP2009-77889
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Topics: Fracture mechanics , Fracture (Materials) , Stress , Damage , Design , Leakage , Manufacturing , Safety , Collapse , Construction
VVER-440 NPP Reactor Vessel and Reactor Internals Design Review Calculation Using ASME BPVC
Tama´s Pa´lfi, Pe´ter Pa´lfi, Sa´ndor Ra´tkai, Sa´ndor Dancso´
PVP 2009; 489-493https://doi.org/10.1115/PVP2009-77908
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Topics: ASME Boiler and Pressure Vessel Code , Design , Nuclear power stations , Reactor vessels , Structural analysis , ASME Standards , Computation , Cycles , Fatigue , Gates (Closures)
Detected Flaw Evaluation on VVER Reactor Components Using ASME Code
Tama´s Pa´lfi, Sa´ndor Ra´tkai
PVP 2009; 495-499https://doi.org/10.1115/PVP2009-77909
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Topics: ASME Standards , Fracture (Materials) , Defect analysis , Finite element analysis , Materials properties , Shapes , Welded joints
Design Review of the VVER-440 NPP Main Components on the Base of ASME BPVC
Ja´nos Boros, Tama´s Pa´lfi, Pe´ter Pa´lfi, Sa´ndor Ra´tkai
PVP 2009; 501-507https://doi.org/10.1115/PVP2009-77910
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Topics: ASME Boiler and Pressure Vessel Code , Design , Nuclear power stations , ASME Standards
Assessment and Management of Ageing of Civil Structures of Paks NPP
Tama´s Katona, Sa´ndor Ra´tkai, Pe´ter Go˝si, Istva´n Mo´ga
PVP 2009; 509-520https://doi.org/10.1115/PVP2009-77911
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Topics: Nuclear power stations , Structures , Concretes , Structural elements (Construction) , Carbon steel , Coating processes , Coatings , Concrete cracking , Corrosion , Licensing
Adaptation of BPVC Section XI Requirements: The Operator’s and the Regulator’s Perspective
P. Babics, S. Ratkai, D. Szabo, P. Trampus
PVP 2009; 521-528https://doi.org/10.1115/PVP2009-77920
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Topics: ASME Boiler and Pressure Vessel Code , ASME Standards , Construction , Design , Inspection , Licensing , Maintenance , Nuclear power stations , Safety
New Safety Assessment System for Corroded Underground Pipelines
Szabolcs Sza´vai, Gyo¨ngyve´r B. Lenkey
PVP 2009; 529-536https://doi.org/10.1115/PVP2009-77959
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Topics: Safety , Underground pipelines , Failure , Pipelines , Pipes , Corrosion , Finite element analysis , Finite element methods , Finite element model , Metals
New PLIM Program for Czech NPPs
Petr Kadecˇka
PVP 2009; 537-544https://doi.org/10.1115/PVP2009-77980
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Topics: Nuclear power stations , Databases , Design , Nuclear research
An Overview of the Research by EC-JRC/IE on Enhancement of Maintenance Efficiency of Nuclear Power Plants
Paolo Contri, Irina Kuzmina
PVP 2009; 545-552https://doi.org/10.1115/PVP2009-78060
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Topics: Maintenance , Nuclear power stations , Optimization , Public utilities
The Effect of Post-Irradiation Annealing on VVER-440 RPV Materials Mechanolocal Properties and Nano-Structure Under Re-Irradiation
S. Rogozkin, A. Chernobaeva, A. Aleev, A. Nikitin, A. Zaluzhnyi, D. Erak, Ya. Shtrombakh, O. Zabusov, L. Debarberis, A. Zeman
PVP 2009; 553-562https://doi.org/10.1115/PVP2009-78128
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Topics: Annealing , Irradiation (Radiation exposure) , Nanostructures , Embrittlement , Atoms , Nuclear power stations , Phase transition temperature , Probes , Surveillance
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