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Proceedings Papers

Underwater Remote Handling Equipment for Reactor Internals Maintenance

Motohiko Kimura, Mitsuaki Shimamura, Tomoyuki Itoh, Nobuhiko Tanaka, Yasuhiro Yuguchi, Katsuhiko Naruse
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 243-251, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22188
https://doi.org/10.1115/ICONE10-22188
View Paper titled, Underwater Remote Handling Equipment for Reactor Internals Maintenance
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Topics: Inspection, Maintenance
Proceedings Papers

Alloy 600 Cracking Prevention and Mitigation

Edward A. Siegel, William M. Connor, David R. Forsyth, Manu Badlani, Paula A. Grendys
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 331-346, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22465
https://doi.org/10.1115/ICONE10-22465
View Paper titled, Alloy 600 Cracking Prevention and Mitigation
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Topics: Alloys, Cracking (Materials), Fracture (Process), Temperature, Pipes, Pressurized water reactors, Fracture (Materials), Service life (Equipment), Base metals, Boiling water reactors
Proceedings Papers

Local Approach of Fracture in the Ductile Regime and Application to VVER Materials

B. Z. Margolin, V. I. Kostylev, E. Keim, R. Chaouadi
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 413-420, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22710
https://doi.org/10.1115/ICONE10-22710
View Paper titled, Local Approach of Fracture in the Ductile Regime and Application to VVER Materials
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Topics: Fracture (Materials), Simulation, Ductile fracture, Finite element analysis, Rupture, Stress, Elongation, Mechanical properties, Numerical analysis, Stress-strain curves
Proceedings Papers

Structural Integrity Assessment of Steam Generator Tubes Using a New EPRI Statistical Approach

Carlos Alexandre de Jesus Miranda, Miguel Mattar Neto
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 347-353, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22473
https://doi.org/10.1115/ICONE10-22473
View Paper titled, Structural Integrity Assessment of Steam Generator Tubes Using a New EPRI Statistical Approach
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Topics: Boilers, Nuclear power stations, Pressurized water reactors, Uncertainty, Wall thickness, Corrosion, Damage, Dimensions, In-service inspection, Maintenance
Proceedings Papers

Inspection and Repair Techniques and Strategies for Alloy 600 PWSCC in Reactor Vessel Head CRD Nozzles and Welds

S. W. Glass, D. M. Schlader
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 421-427, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22743
https://doi.org/10.1115/ICONE10-22743
View Paper titled, Inspection and Repair Techniques and Strategies for Alloy 600 PWSCC in Reactor Vessel Head CRD Nozzles and Welds
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Topics: Alloys, Inspection, Maintenance, Nozzles, Reactor vessels, Welded joints, Leakage, Design, Fracture (Materials), Geometry
Proceedings Papers

Mechanical Properties of 20% Cold-Worked 316 Stainless Steel Irradiated at Low Dose Rate

Todd R. Allen, Hanchung Tsai, James I. Cole, Joji Ohta, Kenji Dohi, Hideo Kusanagi
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 253-259, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22189
https://doi.org/10.1115/ICONE10-22189
View Paper titled, Mechanical Properties of 20% Cold-Worked 316 Stainless Steel Irradiated at Low Dose Rate
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Topics: Mechanical properties, Stainless steel, Fracture (Materials), Fracture (Process), Tensile strength, Ductility, Elongation, Hardening, Work hardening, Brittleness
Proceedings Papers

Short Intergranular Cracks in Elasto-Plastic Polycrystalline Aggregate

Leon Cizelj, Heinz Riesch-Oppermann
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 355-360, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22534
https://doi.org/10.1115/ICONE10-22534
View Paper titled, Short Intergranular Cracks in Elasto-Plastic Polycrystalline Aggregate
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Topics: Fracture (Materials), Stress, Algorithms, Anisotropy, Boilers, Grain size, Modeling, Stress corrosion cracking, Visualization
Proceedings Papers

In-Situ Pressure Testing of Steam Generator Tubes

Cordelia K. Chandler
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 261-266, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22191
https://doi.org/10.1115/ICONE10-22191
View Paper titled, In-Situ Pressure Testing of Steam Generator Tubes
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Topics: Boilers, Pressure testing, Leakage, Condition monitoring, Testing, Tubing, Cycles, Damage, Eddy current testing, Flow measurement
Proceedings Papers

High Cycle Thermal Fatigue in French PWR

Eric Blondet, Claude Faidy
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 429-436, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22762
https://doi.org/10.1115/ICONE10-22762
View Paper titled, High Cycle Thermal Fatigue in French PWR
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Topics: Cycles, Fatigue, Pressurized water reactors, Fracture (Materials), Nozzles, Nuclear power stations, Pipes, Damage, Flow (Dynamics), Fluids
Proceedings Papers

State of Advancement of the International REVE Project: Computational Modelling of Irradiation-Induced Hardening in Reactor Pressure Vessel Steels and Relevant Experimental Validation Programme

Lorenzo Malerba, Eric van Walle, Christophe Domain, Stephanie Jumel, Jean-Claude Van Duysen
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 267-274, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22260
https://doi.org/10.1115/ICONE10-22260
View Paper titled, State of Advancement of the International REVE Project: Computational Modelling of Irradiation-Induced Hardening in Reactor Pressure Vessel Steels and Relevant Experimental Validation Programme
Open the PDF for State of Advancement of the International REVE Project: Computational Modelling of Irradiation-Induced Hardening in Reactor Pressure Vessel Steels and Relevant Experimental Validation Programme in another window
Topics: Hardening, Irradiation (Radiation exposure), Modeling, Reactor vessels, Steel, Dislocations, Feedback, Simulation, Algorithms, Alloys
Proceedings Papers

Failure Pressure and Leak Rate of Steam Generator Tubes With Stress Corrosion Cracks

S. Majumdar, K. Kasza, J. Y. Park, S. Bakhtiari
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 361-366, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22582
https://doi.org/10.1115/ICONE10-22582
View Paper titled, Failure Pressure and Leak Rate of Steam Generator Tubes With Stress Corrosion Cracks
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Topics: Boilers, Failure, Leakage, Pressure, Stress corrosion cracking, Fractography, Fracture (Materials), Nondestructive evaluation, Eddies (Fluid dynamics), Eddy currents (Electricity)
Proceedings Papers

Non-Destructive Techniques in the Tacis and Phare Nuclear Safety Programmes

Michel Bie`th
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 437-441, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22779
https://doi.org/10.1115/ICONE10-22779
View Paper titled, Non-Destructive Techniques in the Tacis and Phare Nuclear Safety Programmes
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Topics: Safety, Design, Nuclear power stations, Circuits, In-service inspection, Fitness-for-service, Licensing, Waste management
Proceedings Papers

Steam Generators Replacement and Power Uprate at Tihange 2 Power Plant

R. Allard, X. Delhaye, J. L. Gre´er, D. Thierens, J. P. Wilmart, R. Ryckaert
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 275-282, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22271
https://doi.org/10.1115/ICONE10-22271
View Paper titled, Steam Generators Replacement and Power Uprate at Tihange 2 Power Plant
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Topics: Boilers, Power stations, Power uprate, Energy engineering, Nuclear fuel cycle, Thermal energy, Safety, Maintenance, Nuclear power stations, Project management
Proceedings Papers

Development of Reconstitution Technology for Surveillance Specimens

Yasushi Atago, Shunichi Hatano, Eiichiro Otsuka
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 367-373, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22629
https://doi.org/10.1115/ICONE10-22629
View Paper titled, Development of Reconstitution Technology for Surveillance Specimens
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Topics: Fracture toughness, Surveillance
Proceedings Papers

Fatigue During Multi-Axial Random Loadings

Joseph Zarka, Habib Karaouni
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 191-198, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22027
https://doi.org/10.1115/ICONE10-22027
View Paper titled, Fatigue During Multi-Axial Random Loadings
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Topics: Construction, Cycles, Damage, Elasticity, Failure, Fatigue, Fatigue analysis, Fatigue testing, Mechanical behavior, Scalars
Proceedings Papers

NDE Performance (POD) Curves for Fatigue Cracks in Piping Based on Industry Performance Demonstration Data

S. R. Gosselin, F. A. Simonen, P. G. Heasler, S. R. Doctor, F. L. Becker
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 293-303, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22418
https://doi.org/10.1115/ICONE10-22418
View Paper titled, NDE Performance (POD) Curves for Fatigue Cracks in Piping Based on Industry Performance Demonstration Data
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Topics: Fatigue cracks, Nondestructive evaluation, Pipes, Stainless steel, Carbon steel, Fracture (Materials), Nuclear power, Probability, Databases, Fracture mechanics
Proceedings Papers

A Study of Steam Generator Aging Management at Selected U.S. Nuclear Plants

James C. Lin
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 199-203, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22069
https://doi.org/10.1115/ICONE10-22069
View Paper titled, A Study of Steam Generator Aging Management at Selected U.S. Nuclear Plants
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Topics: Boilers, Nuclear power stations
Proceedings Papers

An Improved Method for Postulating Fabrication Flaws in Reactor Pressure Vessels for Structural Integrity Evaluation

F. A. Simonen, T. L. Dickson
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 375-382, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22646
https://doi.org/10.1115/ICONE10-22646
View Paper titled, An Improved Method for Postulating Fabrication Flaws in Reactor Pressure Vessels for Structural Integrity Evaluation
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Topics: Manufacturing, Reactor vessels, Vessels, Fracture mechanics, Welded joints, Base metals, Cladding systems (Building), Forgings (Products), Fracture toughness, Maintenance
Proceedings Papers

Emersion Testing of Phe´nix Reactor Components From Liquid Sodium

F. Baque´, L. Martin
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 205-210, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22083
https://doi.org/10.1115/ICONE10-22083
View Paper titled, Emersion Testing of Phe´nix Reactor Components From Liquid Sodium
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Topics: Sodium, Testing, Wetting, Manufacturing, Inspection, Optical quality control, Drainage, Floods, Flow (Dynamics), Fracture (Materials)
Proceedings Papers

Evaluation of the Risk of Damages in Mixing Zones: EDF R&D Programme

J. M. Stephan, F. Curtit, C. Vindeirinho, S. Taheri, M. Akamatsu, C. Peniguel
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 305-310, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22432
https://doi.org/10.1115/ICONE10-22432
View Paper titled, Evaluation of the Risk of Damages in Mixing Zones: EDF R&D Programme
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Topics: Damage, Risk, Nuclear power stations, Cycles, Damage assessment, Fatigue, Fluctuations (Physics), Fracture (Materials), Heat, Steel