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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

Paper No: ICONE10-22646

DOI: https://doi.org/10.1115/ICONE10-22646

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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

Paper No: ICONE10-22083

DOI: https://doi.org/10.1115/ICONE10-22083

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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

Paper No: ICONE10-22432

DOI: https://doi.org/10.1115/ICONE10-22432

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Topics: Damage, Risk, Nuclear power stations, Cycles, Damage assessment, Fatigue, Fluctuations (Physics), Fracture (Materials), Heat, Steel

Proceedings Papers

Evaluation and Repair of Primary Water Stress Corrosion Cracking in Alloy 600/182 Control Rod Drive Mechanism Nozzles

Charles R. Frye, Melvin L. Arey, Jr., Michael R. Robinson, David E. Whitaker

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 383-388, April 14–18, 2002

Paper No: ICONE10-22653

DOI: https://doi.org/10.1115/ICONE10-22653

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Topics: Indium alloys, Maintenance, Nozzles, Stress corrosion cracking, Water, Alloys, Fracture (Materials), Coolants, Crystals, Failure mechanisms

Proceedings Papers

Twenty Years of Operation in NPP Krsko

Kresimir Nemcic, Robert Brems

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 211-215, April 14–18, 2002

Paper No: ICONE10-22130

DOI: https://doi.org/10.1115/ICONE10-22130

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Topics: Nuclear power stations, Boilers, Reliability, Water chemistry, Condensers (steam plant), Corrective actions, Corrosion, Countermeasures, Design, Erosion

Proceedings Papers

Status of the United States Nuclear Regulatory Commission Pressurized Thermal Shock Rule Re-Evaluation Project

Terry L. Dickson, Shah N. Malik, Mark T. Kirk, Deborah A. Jackson

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 389-397, April 14–18, 2002

Paper No: ICONE10-22656

DOI: https://doi.org/10.1115/ICONE10-22656

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Topics: Thermal shock, Regulations, Pressurized water reactors, Human reliability analysis, Nuclear industry, Relaxation (Physics), Risk, Transients (Dynamics), Computers, Embrittlement

Proceedings Papers

A Foundation for Stressor-Based Prognostics for Next Generation Systems

Don Jarrell, Daniel Sisk, Leonard Bond

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 311-319, April 14–18, 2002

Paper No: ICONE10-22458

DOI: https://doi.org/10.1115/ICONE10-22458

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Topics: Bearings, Cavitation, Centrifugal pumps, Engines, Equipment performance, Failure, Lasers, Machinery, Maintenance, Monitoring systems

Proceedings Papers

U.S. Operating Experience With Thermally Treated Alloy 600 Steam Generator Tubes

April Smith, Kenneth J. Karwoski

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 217-225, April 14–18, 2002

Paper No: ICONE10-22139

DOI: https://doi.org/10.1115/ICONE10-22139

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Topics: Alloys, Boilers

Proceedings Papers

Repair Welding of Irradiated Materials: Modeling of Helium Bubble Distributions for Determining Crack-Free Welding Procedures

Zhili Feng, Gery Wilkowski

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 399-406, April 14–18, 2002

Paper No: ICONE10-22660

DOI: https://doi.org/10.1115/ICONE10-22660

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Topics: Bubbles, Fracture (Materials), Helium, Maintenance, Modeling, Welding, Stress, Cracking (Materials), Finite element model, Fracture (Process)

Proceedings Papers

Evaluation of NDE Round-Robin Exercises Using the NRC Steam Generator Mockup at Argonne National Laboratory

Joseph Muscara, David S. Kupperman, Sasan Bakhtiari, Jang-Yul Park, William J. Shack

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 321-329, April 14–18, 2002

Paper No: ICONE10-22464

DOI: https://doi.org/10.1115/ICONE10-22464

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Topics: Boilers, Nondestructive evaluation, Fracture (Materials), Probes, Eddies (Fluid dynamics), Eddy currents (Electricity), Engineering simulation, Errors, Reliability, Simulation

Proceedings Papers

Evaluation of Mechanical Properties of Nuclear Materials Using Non-Destructive Ball Indentation Technique

M. D. Mathew, K. Linga Murty

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 227-233, April 14–18, 2002

Paper No: ICONE10-22150

DOI: https://doi.org/10.1115/ICONE10-22150

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Topics: Mechanical properties, Fracture toughness, Deformation, Nondestructive evaluation, Steel, Anisotropy, Cladding systems (Building), Fracture (Materials), Fracture (Process), Heat

Proceedings Papers

BWR In-Core Monitor Housing Replacement Under Dry Condition of Reactor Pressure Vessel

Tatsuo Ishida, Shoji Yamamoto, Fujitoshi Eguchi, Motomasa Fuse, Kouichi Kurosawa, Sadato Shimizu, Minoru Masuda, Shinya Fujii, Junji Tanaka, Bryce A. Jacobson

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 407-412, April 14–18, 2002

Paper No: ICONE10-22679

DOI: https://doi.org/10.1115/ICONE10-22679

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Topics: Boiling water reactors, Reactor vessels, Pipes, Radiation (Physics), Water

Proceedings Papers

e-chem page : A Support System for Remote Diagnosis of Water Quality in Boiling Water Reactors

Naohiro Kusumi, Takayasu Kasahara, Kazuhiko Akamine, Kenji Tada, Naoshi Usui, Nobuyuki Oota

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 1, 235-241, April 14–18, 2002

Paper No: ICONE10-22162

DOI: https://doi.org/10.1115/ICONE10-22162

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Topics: Boiling water reactors, Chemistry, Independent component analysis, Water pollution

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

Paper No: ICONE10-22188

DOI: https://doi.org/10.1115/ICONE10-22188

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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

Paper No: ICONE10-22465

DOI: https://doi.org/10.1115/ICONE10-22465

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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

Paper No: ICONE10-22710

DOI: https://doi.org/10.1115/ICONE10-22710

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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

Paper No: ICONE10-22473

DOI: https://doi.org/10.1115/ICONE10-22473

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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

Paper No: ICONE10-22743

DOI: https://doi.org/10.1115/ICONE10-22743

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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

Paper No: ICONE10-22189

DOI: https://doi.org/10.1115/ICONE10-22189

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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

Paper No: ICONE10-22534

DOI: https://doi.org/10.1115/ICONE10-22534

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Topics: Fracture (Materials), Stress, Algorithms, Anisotropy, Boilers, Grain size, Modeling, Stress corrosion cracking, Visualization

NARROW

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

Emersion Testing of Phe´nix Reactor Components From Liquid Sodium

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

Evaluation and Repair of Primary Water Stress Corrosion Cracking in Alloy 600/182 Control Rod Drive Mechanism Nozzles

Twenty Years of Operation in NPP Krsko

Status of the United States Nuclear Regulatory Commission Pressurized Thermal Shock Rule Re-Evaluation Project

A Foundation for Stressor-Based Prognostics for Next Generation Systems

U.S. Operating Experience With Thermally Treated Alloy 600 Steam Generator Tubes

Repair Welding of Irradiated Materials: Modeling of Helium Bubble Distributions for Determining Crack-Free Welding Procedures

Evaluation of NDE Round-Robin Exercises Using the NRC Steam Generator Mockup at Argonne National Laboratory

Evaluation of Mechanical Properties of Nuclear Materials Using Non-Destructive Ball Indentation Technique

BWR In-Core Monitor Housing Replacement Under Dry Condition of Reactor Pressure Vessel

e-chem page : A Support System for Remote Diagnosis of Water Quality in Boiling Water Reactors

Underwater Remote Handling Equipment for Reactor Internals Maintenance

Alloy 600 Cracking Prevention and Mitigation

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

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

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

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

Short Intergranular Cracks in Elasto-Plastic Polycrystalline Aggregate

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