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Safety, Reliability, and Risk Assessment |
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1 | (2) |
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Counterfeit and Rogue Industrial Parts and Materials, and Their Impact on Safety and Reliability |
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3 | (4) |
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Evaluation of Damage of Steam Pipeline Steel Using Local Approach to Fracture |
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7 | (6) |
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Fuzzy Risk Analysis for the Urban Buried Gas Pipeline |
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13 | (8) |
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CFD Numerical Simulation of the Submarine Pipeline With Spoiler |
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21 | (8) |
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Reliability-Based Material Selection for Glycol Evaporator of PTA Installation |
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29 | (6) |
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Analytical Solutions and Tools for Assessment of Surface Cracks in Cylindrical Components |
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35 | (12) |
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Service Water Life Cycle Management |
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47 | (6) |
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A Global Limit Load Solution for Plates With Embedded Elliptical Cracks Under Combined Tension and Bending |
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53 | (6) |
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Effects of Negative Biaxial Loadings and Notch on Failure Assessment Diagrams |
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59 | (10) |
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Qualification and Testing: Pressure Vessels, Piping, Components and Structures |
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69 | (2) |
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Experience With Extended Power Uprate at Leibstadt Nuclear Power Plant |
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71 | (8) |
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Evaluation of Structural Integrity for a Dry Storage System With Spacer Disks in a Scale Model Drop Test |
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79 | (10) |
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Nuclear PWR Plants: Managing the Expertise on Cast Components Removed From Reactor Coolant Circuit |
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89 | (10) |
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Recent Reactor Head Drop Analysis for Complying NUREG-0612 Appendix A Guidelines |
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99 | (20) |
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Monitoring, Diagnostics and Inspection |
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119 | (2) |
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On-Board Dynamic Strain System for Turbine Engine Ground Testing |
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121 | (8) |
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Ways for Extending the Reactor Pressure Vessel Lifetime |
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129 | (8) |
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Application of Time Synchronous Averaging, Spectral Kurtosis and Support Vector Machines for Bearing Fault Identification |
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137 | (10) |
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Christian N. Komgom Nguepjop |
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On Leak Detection of Pipeline Using Computational Pipeline Monitoring |
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147 | (8) |
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155 | (2) |
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Temperature Prediction in 3013 Containers in K-Area Material Storage (KAMS) Facility Using Regression Methods |
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157 | (8) |
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Comparison of Response of 9977 Test Packages to Analytical Results |
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165 | (8) |
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Model 9975 Shipping Package Fabrication Problems and Solutions |
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173 | (6) |
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Finite Element Mesh Considerations for Reduced Integration Elements |
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179 | (4) |
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Impact Testing of Stainless Steel Material at Cold Temperatures |
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183 | (12) |
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The Department of Energy Replacement for the 110-Gallon Specification 6M Shipping Container for Radioactive Contents |
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195 | (6) |
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Effect of Chemistry Variations of Wrought N06022 Plates on the Repassivation Potential in 1 M NaCl at 90°C |
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201 | (8) |
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The Long-Term Environmental Degradation of Zirconium Alloys in Contact With Spent Nuclear Fuel: A Review |
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209 | (6) |
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Uncertainty of Preloads in Closure Bolts for Transportation Casks for Hazardous and Radioactive Materials |
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215 | (10) |
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Recent Development of Code Case on Use of Ductile Cast Iron for Transport and Storage Cask for Spent Nuclear Fuel |
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225 | (10) |
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Foam Density Sensitivity Study for the 9977 Package |
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235 | (10) |
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Analytical and Numerical Evaluation of the Impact Limiters Design of a Research Reactor Spent Fuel Transportation Package Half Scale Model Under 9 M Drop Tests |
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245 | (6) |
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Risk Perspectives on Rail Transport of Spent Nuclear Fuel |
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251 | (4) |
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Dynamic Analysis of Hanford Unirradiated Fuel Package Subjected to Sequential Lateral Loads in Hypothetical Accident Conditions |
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255 | (8) |
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Potential Effects of Recent Road Transportation Accidents on Radioactive Material Shipments |
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263 | (8) |
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CFD Simulations of an 8X8 Rod Array Inside of an Insothermal Enclosure Filled With a Rarified Gas |
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271 | (8) |
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Evaluation of Thermal Conductivity of Installed-in-Place Polyurethane Foam Insulation by Experiment and Analysis |
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279 | (6) |
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Measurement and Uncertainty of Heat Flux to a Rail-Cask Size Pipe Calorimeter in a Pool Fire |
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285 | (8) |
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Development of Testing Methodologies for Onsite Radioactive Material Storage Containers |
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293 | (6) |
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Headspace Gas Evaluation of Welded Plutonium Storage Containers |
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299 | (8) |
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307 | (2) |
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A Non-Destructive Testing Method and Analysis for Air Pressure Distribution in the Stacks of Building Drainage Systems |
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309 | (8) |
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Implementation of Load Reducing Bushings for Valves in a High Vibration Environment |
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317 | (6) |
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An Evaluation of Post-LOCA Debris on Multi-Stage Safety-Related Pumps in PWR ECCS in Support of Generic Safety Issue 191 Closure |
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323 | (6) |
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Operations and Maintenance of Pressure Vessels, Heat Exchangers and Structures |
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329 | (2) |
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Simulation of Leakage Behavior on Bolted Flanged Connections in Elevated Temperature Service |
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331 | (10) |
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Buckling Characteristics of Floating Roof Pontoons in Aboveground Storage Tanks Subjected to Bending Load in Two Directions |
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341 | (10) |
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Eulerian Finite Element Formulation for Sloshing Response of Floating Roofs in Aboveground Storage Tanks |
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351 | (10) |
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Heat Exchanger Tubular Inspection: A User's Perspective |
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361 | (6) |
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Acceptance Criteria for Repair Method Using Fillet Welded Patches |
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367 | (4) |
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Discussion of Issues Related to Surge in LNG Pipelines at Offloading Terminals |
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371 | (6) |
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Application, Design and Operation Considerations for Brazed Aluminum Heat Exchangers in Liquefied Natural Gas Service |
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377 | (10) |
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Vaporization of LNG Using Fired Heaters With Waste Heat Recovery |
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387 | (6) |
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Creep Damage Analysis of High Pressurized Steam Pipelines Using Omega Method |
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393 | (8) |
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Development of a Dissimilar Temper Bead Welding Procedure for Amine Tower Repair |
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401 | (10) |
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Experimental and Numerical Validation of Fitness-for-Service Assessment for Cylindrical and Spherical Pressure Vessel With Local Metal Loss |
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411 | (6) |
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Earthquake Resistant Design Code and Validation of Local Metal Loss Procedure Based on the Experimental Data Collected in Japan |
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417 | (8) |
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Development of Repair Welding Guidelines on Pressure Equipment |
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425 | (8) |
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Repair Welding of Long-Term Used Ethylene Pyrolysis Radiant Tubes |
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433 | (6) |
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Repair Weldability at Overlay/Base Metal Interface of Petroleum Pressure Vessel |
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439 | (8) |
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447 | (2) |
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Residual Stress Modeling of Warm-Bent Tight-Radius CANDU Feeder Bends |
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449 | (8) |
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Elastic-Plastic Fracture Mechanics Method for Poor Penetration Crack in Welded Piping Branch Junction |
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457 | (10) |
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Theoretical Analysis and Numerical Simulation on the Hydraulic Expansion of Double-Layered Tubes |
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467 | (10) |
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Long-Term Stress Analysis of Plastic Pipe Reinforced by Cross-Winding Steel Wire |
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477 | (16) |
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Aging Management and Life Extension of Pressure Vessels and Piping |
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493 | (2) |
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Equipment Reliability: When Utility Meets Manufacturing |
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495 | (10) |
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Modeling and Verification of Creep Strain and Exhaustion in a Welded Steam Mixer |
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505 | (6) |
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Test Programs for Degraded Core Shroud and PLR System Piping: Seismic Test Results and Discussion on JSME Rules Application |
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511 | (10) |
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Developments In Combined ARCMAC and Strain Mapping Systems for Creep Measuremen |
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521 | (8) |
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Recent Developments in Methods to Study Creep Strain Variations in Power Station Steam Plant |
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529 | (8) |
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Complex Monitoring Programme for WWER Reactor Pressure Vessels Lifetime Assessment in the Czech Republic |
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537 | (12) |
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A New Heat Treatment Technology for On-Site Life Extension of High Energy Pipe Weldments Degraded by Creep Damage |
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549 | (6) |
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``Adaptative'' User Interface as a Support for Evaluation Analysis in the Context of Asset Management |
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555 | (14) |
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Assessment of the Real Fatigue Usage of the Volume Control System |
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569 | (10) |
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Nuclear PWR Plants Life Management Reactor Pressure Vessel Strategy Evaluation for Fluence in Relation With Integrity Assessment |
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579 | (10) |
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License Renewal: Status of Long Term Operation in the U.S. |
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589 | (8) |
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Engineering Approach for the Reactor Pressure Vessel Integrity in PTS Conditions: Thermal Hydraulic and Fracture Mechanics Studies of a Safety Injection in a Three Loop Power Plant --- French Benchmark With EDF and AREVA-NP Tools |
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597 | (8) |
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Plant Life Management Models: A Comparison With Analysis of Impact on Both Safety and Non-Safety Issues |
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605 | (8) |
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Plant Life Management of EDF PWR Nuclear Fleet and EPR Flamanville 3 Design: Safety and Pressure Vessels Requirements |
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613 | (8) |
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Regulations, Codes and Standards |
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621 | (2) |
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Certification of the NAC-LWT Cask for Shipment of Sodium Debris Bed Experiments |
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623 | (8) |
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A Proposed Methodology for Strain-Based Failure Criteria |
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631 | (8) |
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A Comparison of 10 CFR 71 and the IAEA TS-R-1 Radioactive Material Transportation Regulations |
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639 | (4) |
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Strain-Based Acceptance Criteria for Inelastic Analysis |
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643 | (8) |
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| Author Index |
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651 | |
