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Proceedings Papers

Proceedings Volume Cover
10th International Conference on Nuclear Engineering
April 14–18, 2002
Arlington, Virginia, USA
Conference Sponsors:
  • Nuclear Engineering Division
ISBN:
0-7918-3595-2
10th International Conference on Nuclear Engineering, Volume 1

Plant Operations and Maintenance

Applicability of Operational Research Techniques in CANDU Nuclear Plant Maintenance
E. Kevin Doyle
ICONE 2002; 1-9https://doi.org/10.1115/ICONE10-22011
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Topics: Complex systems , Containment , Design , Engineers , Errors , Failure , Failure data , Maintenance , Nuclear power , Nuclear power plant maintenance
Developing Predictive Maintenance Expertise to Improve Plant Equipment Reliability
Richard N. Wurzbach
ICONE 2002; 11-18https://doi.org/10.1115/ICONE10-22032
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Topics: Maintenance , Reliability , Energy generation , Nuclear power stations , Safety , Computer software , Condition monitoring , Instrumentation , Profitability , Teams
A Study of Outage Management Practices at Selected U.S. Nuclear Plants
James C. Lin
ICONE 2002; 19-23https://doi.org/10.1115/ICONE10-22068
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Topics: Nuclear power stations , Boiling water reactors , Pressurized water reactors
Maintenance for the Millennium: Another Approach
Barry R. Sculthorpe
ICONE 2002; 25-28https://doi.org/10.1115/ICONE10-22074
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Topics: Maintenance , Machinery , Reliability , Engines , Equipment performance , Lubricants , Metals , Motors , Nuclear power stations , Tribology
A Dynamic Performance Analysis on CANDU Fuel Handling System for Operational Improvement
Jeong Mann Kim, Byung Ryul Jung, Wan Kyu Park
ICONE 2002; 29-36https://doi.org/10.1115/ICONE10-22091
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Topics: Computers , Control systems , Dynamic analysis , Fuels , Machinery , Modeling , Nuclear power stations , Pressure , Pressure control , Valves
Computed Radiography: An Innovative Inspection Technique
William A. Klein, Donald L. Councill
ICONE 2002; 37-40https://doi.org/10.1115/ICONE10-22102
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Topics: Inspection , Corrosion , Reliability , Safety , Biomedicine , Flow (Dynamics) , Insulation , Pipes , Valves
Operational Events Noted for Power Uprated Plants and Potential Safety Implications
A. W. Cronenberg, D. A. Powers, R. P. Savio
ICONE 2002; 41-46https://doi.org/10.1115/ICONE10-22123
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Topics: Safety , Power uprate , Failure , Fuels , Licensing , Light water reactors , Pipes , Pressurized water reactors , Regulations , Rods
Managing the Cost of Plant Piping System Leakage
John M. Jenco, Donna R. Keck, Gary L. Johnson
ICONE 2002; 47-52https://doi.org/10.1115/ICONE10-22193
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Topics: Leakage , Piping systems , Fluids , Maintenance , Nuclear power plant operations , Public utilities
Sensitivity Degradation Characteristics of Incore Neutron Detector for Heavy Water Reactor, Fugen NPP
Tsuyoshi Okawa, Naoyuki Yomori
ICONE 2002; 53-60https://doi.org/10.1115/ICONE10-22234
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Topics: Fuels , Heavy water reactors , Neutrons , Nuclear fission , Nuclear power stations , Sensors
A Model for Shortening the Length of Activities in Construction and Overhaul Planning: UPROB
Niko Majdandzˇic´, Slavko Sebastijanovic´, Gordana Maticˇevic´, Nebojsˇa Sebastijanovic´
ICONE 2002; 61-66https://doi.org/10.1115/ICONE10-22239
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Topics: Construction , Assembly lines , Databases , Thermal energy
Increase of Steam Moisture in the BWR-Facility KKP 1
Volker Noack
ICONE 2002; 67-70https://doi.org/10.1115/ICONE10-22266
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Topics: Boiling water reactors , Leakage , Steam
Managing Feedwater Heater Shell Thinning
John W. Simons, Robert B. Keating
ICONE 2002; 71-75https://doi.org/10.1115/ICONE10-22302
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Topics: Feedwater , Shells , Maintenance , Wall thickness , Acceptance criteria , ASME Standards , Inspection , Steam , Nozzles , Nuclear industry
Increased Availability From Improved Condenser Design
Joseph W. Harpster
ICONE 2002; 77-84https://doi.org/10.1115/ICONE10-22318
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Topics: Condensers (steam plant) , Design , Gases , Condensed matter , Corrosion , Dynamic models , Dynamics (Mechanics) , Engineering design , Flow (Dynamics) , Fuels
Corrosion Resistant Cladding by YAG Laser Welding in Underwater Environment
Tsutomu Kochi, Toshio Kojima, Suemi Hirata, Ichiro Morita, Katsura Ohwaki
ICONE 2002; 85-107https://doi.org/10.1115/ICONE10-22327
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Topics: Cladding systems (Building) , Corrosion , Laser welding , Water , Lasers , Nozzles , Stress , Welding , Alloys , Drainage
On-Line Monitoring of Instrument Channel Performance in Nuclear Power Plant Using PEANO
Paolo F. Fantoni, Mario Hoffmann, Ramesh Shankar, Eddie L. Davis
ICONE 2002; 109-113https://doi.org/10.1115/ICONE10-22345
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Topics: Artificial intelligence , Instrumentation , Nuclear power stations , Calibration , Performance characterization , Pressurized water reactors , Radiation (Physics) , Signals , Testing performance
Benefits of Digital Equipment Generic Qualification Activities
James E. Thomas, Samuel C. Steiman
ICONE 2002; 115-117https://doi.org/10.1115/ICONE10-22380
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Topics: Design , Electricity (Physics) , Electromagnetic compatibility , Instrumentation , Nuclear power stations , Safety
Studies on Applicability of Smoke Sensors as a Sodium Leak Monitoring System
Koji Morizono, Yuji Maruta, Makinori Ikeda
ICONE 2002; 119-122https://doi.org/10.1115/ICONE10-22459
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Topics: Leakage , Monitoring systems , Sensors , Smoke , Sodium
Emergency Diesel Generator System Surveillance Test Policy Optimization Through Genetic Algorithms Using Non-Periodic Intervention Frequencies and Seasonal Constraints
Celso M. F. Lapa, Cla´udio M. N. A. Pereira, P. F. Frutuoso e Melo
ICONE 2002; 123-128https://doi.org/10.1115/ICONE10-22496
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Topics: Diesel generators , Emergencies , Genetic algorithms , Optimization , Surveillance , Probability , Nuclear power stations , Diesel , Electricity (Physics) , Failure
Life Cycle Management: Managing the Aging of Critical Nuclear Plant Components
Theodore A. Meyer, G. Gary Elder, Ricardo Llovet
ICONE 2002; 129-136https://doi.org/10.1115/ICONE10-22536
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Topics: Life cycle management , Nuclear power stations , Maintenance , Reliability , Safety
In-Situ Calibration for Feedwater Flow Measurement
David Peyvan, Yuri Gurevich, Charles T. French
ICONE 2002; 137-142https://doi.org/10.1115/ICONE10-22538
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Topics: Calibration , Feedwater , Flow (Dynamics) , Flow measurement
Remote-Controlled Inspection Robot for Nuclear Facilities in Underwater Environment
Yasuhiro Miwa, Syuichi Satoh, Naoya Hirose
ICONE 2002; 143-152https://doi.org/10.1115/ICONE10-22560
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Topics: Inspection , Nuclear power stations , Robots
Impact of Flow Velocity Profile on Ultrasonic Measurement Accuracy for Feedwater Flow in Nuclear Power Plants
E. Hauser, J. Regan, H. Estrada
ICONE 2002; 153-159https://doi.org/10.1115/ICONE10-22591
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Topics: Feedwater , Flow (Dynamics) , Nuclear power stations , Ultrasonic measurement , Pipes , Flow measurement , Pipe fittings , Surface roughness
The Joint Owners’ Group Program on MOV Periodic Verification
Paul S. Damerell, Todd A. Spears
ICONE 2002; 161-174https://doi.org/10.1115/ICONE10-22599
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Topics: Bearings , Boiling water reactors , Bronze , Combustion engineering , Engines , Flow (Dynamics) , Friction , Gates (Closures) , Motors , Pressure
Major Component Replacement Experience in IKATA Power Station
Yoshihisa Asai, Toshimitsu Takagi, Tatsuya Azuma
ICONE 2002; 175-179https://doi.org/10.1115/ICONE10-22618
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Topics: Power stations , Boilers , Pressurized water reactors , Reactor vessels
The Need for Strategic Planning for Nuclear Power Plant I&C Upgrades
J. Douglas Hill, Paul Moore
ICONE 2002; 181-183https://doi.org/10.1115/ICONE10-22626
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Topics: Nuclear power stations , Strategic planning , Design , Economics , Instrumentation , Power station control systems
Inspection Guideline of BWR Core Internals in Japan
Akio Yamamoto, Naoto Iizuka, Takeshi Yoshinaga, Haruo Fujimori, Yuuichi Motora
ICONE 2002; 185-189https://doi.org/10.1115/ICONE10-22717
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Topics: Boiling water reactors , Inspection , Evaluation methods , Fracture (Materials) , Jet pumps , Nuclear engineering , Public utilities

Major Component Reliability and Materials Issues

Fatigue During Multi-Axial Random Loadings
Joseph Zarka, Habib Karaouni
ICONE 2002; 191-198https://doi.org/10.1115/ICONE10-22027
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Topics: Construction , Cycles , Damage , Elasticity , Failure , Fatigue , Fatigue analysis , Fatigue testing , Mechanical behavior , Scalars
A Study of Steam Generator Aging Management at Selected U.S. Nuclear Plants
James C. Lin
ICONE 2002; 199-203https://doi.org/10.1115/ICONE10-22069
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Topics: Boilers , Nuclear power stations
Emersion Testing of Phe´nix Reactor Components From Liquid Sodium
F. Baque´, L. Martin
ICONE 2002; 205-210https://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)
Twenty Years of Operation in NPP Krsko
Kresimir Nemcic, Robert Brems
ICONE 2002; 211-215https://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
U.S. Operating Experience With Thermally Treated Alloy 600 Steam Generator Tubes
April Smith, Kenneth J. Karwoski
ICONE 2002; 217-225https://doi.org/10.1115/ICONE10-22139
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Topics: Alloys , Boilers
Evaluation of Mechanical Properties of Nuclear Materials Using Non-Destructive Ball Indentation Technique
M. D. Mathew, K. Linga Murty
ICONE 2002; 227-233https://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
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
ICONE 2002; 235-241https://doi.org/10.1115/ICONE10-22162
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Topics: Boiling water reactors , Chemistry , Independent component analysis , Water pollution
Underwater Remote Handling Equipment for Reactor Internals Maintenance
Motohiko Kimura, Mitsuaki Shimamura, Tomoyuki Itoh, Nobuhiko Tanaka, Yasuhiro Yuguchi, Katsuhiko Naruse
ICONE 2002; 243-251https://doi.org/10.1115/ICONE10-22188
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Topics: Inspection , Maintenance
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
ICONE 2002; 253-259https://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
In-Situ Pressure Testing of Steam Generator Tubes
Cordelia K. Chandler
ICONE 2002; 261-266https://doi.org/10.1115/ICONE10-22191
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Topics: Boilers , Pressure testing , Leakage , Condition monitoring , Testing , Tubing , Cycles , Damage , Eddy current testing , Flow measurement
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
ICONE 2002; 267-274https://doi.org/10.1115/ICONE10-22260
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Topics: Hardening , Irradiation (Radiation exposure) , Modeling , Reactor vessels , Steel , Dislocations , Feedback , Simulation , Algorithms , Alloys
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
ICONE 2002; 275-282https://doi.org/10.1115/ICONE10-22271
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Topics: Boilers , Power stations , Power uprate , Energy engineering , Nuclear fuel cycle , Thermal energy , Safety , Maintenance , Nuclear power stations , Project management
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
ICONE 2002; 293-303https://doi.org/10.1115/ICONE10-22418
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Topics: Fatigue cracks , Nondestructive evaluation , Pipes , Stainless steel , Carbon steel , Fracture (Materials) , Nuclear power , Probability , Databases , Fracture mechanics
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
ICONE 2002; 305-310https://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
A Foundation for Stressor-Based Prognostics for Next Generation Systems
Don Jarrell, Daniel Sisk, Leonard Bond
ICONE 2002; 311-319https://doi.org/10.1115/ICONE10-22458
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Topics: Bearings , Cavitation , Centrifugal pumps , Engines , Equipment performance , Failure , Lasers , Machinery , Maintenance , Monitoring systems
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
ICONE 2002; 321-329https://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
Alloy 600 Cracking Prevention and Mitigation
Edward A. Siegel, William M. Connor, David R. Forsyth, Manu Badlani, Paula A. Grendys
ICONE 2002; 331-346https://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
Structural Integrity Assessment of Steam Generator Tubes Using a New EPRI Statistical Approach
Carlos Alexandre de Jesus Miranda, Miguel Mattar Neto
ICONE 2002; 347-353https://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
Short Intergranular Cracks in Elasto-Plastic Polycrystalline Aggregate
Leon Cizelj, Heinz Riesch-Oppermann
ICONE 2002; 355-360https://doi.org/10.1115/ICONE10-22534
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Topics: Fracture (Materials) , Stress , Algorithms , Anisotropy , Boilers , Grain size , Modeling , Stress corrosion cracking , Visualization
Failure Pressure and Leak Rate of Steam Generator Tubes With Stress Corrosion Cracks
S. Majumdar, K. Kasza, J. Y. Park, S. Bakhtiari
ICONE 2002; 361-366https://doi.org/10.1115/ICONE10-22582
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Topics: Boilers , Failure , Leakage , Pressure , Stress corrosion cracking , Fractography , Fracture (Materials) , Nondestructive evaluation , Eddies (Fluid dynamics) , Eddy currents (Electricity)
Development of Reconstitution Technology for Surveillance Specimens
Yasushi Atago, Shunichi Hatano, Eiichiro Otsuka
ICONE 2002; 367-373https://doi.org/10.1115/ICONE10-22629
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Topics: Fracture toughness , Surveillance
An Improved Method for Postulating Fabrication Flaws in Reactor Pressure Vessels for Structural Integrity Evaluation
F. A. Simonen, T. L. Dickson
ICONE 2002; 375-382https://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
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
ICONE 2002; 383-388https://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
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
ICONE 2002; 389-397https://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
Repair Welding of Irradiated Materials: Modeling of Helium Bubble Distributions for Determining Crack-Free Welding Procedures
Zhili Feng, Gery Wilkowski
ICONE 2002; 399-406https://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)
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
ICONE 2002; 407-412https://doi.org/10.1115/ICONE10-22679
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Topics: Boiling water reactors , Reactor vessels , Pipes , Radiation (Physics) , Water
Local Approach of Fracture in the Ductile Regime and Application to VVER Materials
B. Z. Margolin, V. I. Kostylev, E. Keim, R. Chaouadi
ICONE 2002; 413-420https://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
Inspection and Repair Techniques and Strategies for Alloy 600 PWSCC in Reactor Vessel Head CRD Nozzles and Welds
S. W. Glass, D. M. Schlader
ICONE 2002; 421-427https://doi.org/10.1115/ICONE10-22743
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Topics: Alloys , Inspection , Maintenance , Nozzles , Reactor vessels , Welded joints , Leakage , Design , Fracture (Materials) , Geometry
High Cycle Thermal Fatigue in French PWR
Eric Blondet, Claude Faidy
ICONE 2002; 429-436https://doi.org/10.1115/ICONE10-22762
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Topics: Cycles , Fatigue , Pressurized water reactors , Fracture (Materials) , Nozzles , Nuclear power stations , Pipes , Damage , Flow (Dynamics) , Fluids
Non-Destructive Techniques in the Tacis and Phare Nuclear Safety Programmes
Michel Bie`th
ICONE 2002; 437-441https://doi.org/10.1115/ICONE10-22779
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Topics: Safety , Design , Nuclear power stations , Circuits , In-service inspection , Fitness-for-service , Licensing , Waste management

Structural Integrity, Dynamics and Mitigation, Material and Failure

Evaluation of Continuous Low-Cycle Fatigue Behaviour of High Temperature P122 Boiler Material
John Pumwa, Soo Woo Nam
ICONE 2002; 443-452https://doi.org/10.1115/ICONE10-22012
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Topics: Boilers , High temperature , Low cycle fatigue , Fracture (Materials) , Fracture (Process) , Stress , Control equipment , Creep , Cycles , Machinery
Analysis of Particle-Dispersed Composites Accounting Stochastically for Interfacial Damage
Huajian Chang, Michihiko Nakagaki
ICONE 2002; 453-459https://doi.org/10.1115/ICONE10-22017
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Topics: Accounting , Composite materials , Damage , Particulate matter , Displacement , Tensors , Constitutive equations , Stress , Deformation , Nuclear power stations
J Resistance Curve Estimation of Inhomogeneous CT Specimen
Kiminobu Hojo, Kazutoshi Ohoto, Itaru Muroya
ICONE 2002; 461-482https://doi.org/10.1115/ICONE10-22047
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Topics: ASTM International , Finite element analysis , Fracture toughness , Plane strain , Stress
Assessment of Aging of Nuclear Power Plant Civil Structures
D. J. Naus, B. R. Ellingwood, H. L. Graves, III
ICONE 2002; 483-491https://doi.org/10.1115/ICONE10-22067
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Topics: Nuclear power stations , Containment , Pressure , Reinforced concrete , Event history analysis , Inspection , Light water reactors , Steel
Transverse Vibrations of Single Bellows Expansion Joint Restrained Against Rotation
C. Kameswara Rao, M. Radhakrishna
ICONE 2002; 493-497https://doi.org/10.1115/ICONE10-22090
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Topics: Bellows expansion joints , Rotation , Vibration
Transverse Vibrations of Double Bellows Expansion Joint Restrained Against Rotation
C. Kameswara Rao, M. Radhakrishna
ICONE 2002; 499-506https://doi.org/10.1115/ICONE10-22092
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Topics: Bellows expansion joints , Rotation , Vibration
Load Regime Diagram of a Pipe With Cyclically Plastic Bending
Yanping Yao, Ming-Wan Lu
ICONE 2002; 507-512https://doi.org/10.1115/ICONE10-22100
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Topics: Pipes , Stress
Effects of Dynamic Strain-Aging and Cyclic Loading on Fracture Behavior of Ferritic Steels
K. Linga Murty, Chang-Sung Seok
ICONE 2002; 513-518https://doi.org/10.1115/ICONE10-22151
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Topics: Fracture (Materials) , Steel , Stress , Fracture toughness , Displacement , Radiation (Physics) , Work hardening , Ductility , Iron , Light water reactors
A Study of Cavitation Erosion
Hiromu Isaka, Masatsugu Tsutsumi, Hiroyuki Kobayashi, Tadashi Shiraishi
ICONE 2002; 519-525https://doi.org/10.1115/ICONE10-22172
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Topics: Cavitation erosion , Cavitation , Design , Erosion , Pressurized water reactors , Stainless steel , Hard materials , Hardening , High pressure (Physics) , Orifices
A Contribution to Proof the Component Integrity Taking Into Account the Corrosion-Assisted Crack Growth
Eberhard Roos, Frank Otremba, Frank Hu¨ttner
ICONE 2002; 527-531https://doi.org/10.1115/ICONE10-22175
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Topics: Corrosion , Fracture (Materials) , Stress , Databases , Nuclear power stations , Steel , Alloys , Coolants , Cycles , Damage
Impact Analysis of a Dipper-Type and Multi Spring-Type Fuel Rod Support Grid Assemblies in PWR
K. N. Song, K. J. Park, K. H. Yoon, G. J. Park, B. S. Kang
ICONE 2002; 533-540https://doi.org/10.1115/ICONE10-22177
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Topics: Fuel rods , Pressurized water reactors , Springs , Stress , Simulation , Computer software , Cooling , Deformation , Design , Finite element analysis
Design of a Spacer Grid Using Axiomatic Design
K. N. Song, B. S. Kang, K. H. Yoon, S. K. Choi, G. J. Park
ICONE 2002; 541-549https://doi.org/10.1115/ICONE10-22178
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Topics: Design , Fuels , Shapes , Conceptual design , Cooling , Dimensions , Finite element analysis , Fuel rods , Geometry , Light water reactors
Assessment of Ultimate Load Capacity for Pre-Stressed Concrete Containment Vessel Model of PWR Design With BARC Code ULCA
S. M. Basha, R. K. Singh, R. Patnaik, S. Ramanujam, H. S. Kushwaha, V. Venkat Raj
ICONE 2002; 551-561https://doi.org/10.1115/ICONE10-22187
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Topics: Containment vessels , Design , Pressurized water reactors , Prestressed concrete , Stress , Pressure , Heavy water reactors , Failure , Concretes , Construction
Vibration Analysis of a Multispan Tube in a Bundle
Shahab Khushnood, Zaffar M. Khan, M. Afzaal Malik, Zafar Ullah Koreshi, Mehmood Anwer Khan
ICONE 2002; 563-572https://doi.org/10.1115/ICONE10-22210
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Topics: Computers , Damping , Design , Failure , Flow (Dynamics) , Heat exchangers , Pipes , Process industries , Turbulence , Vibration
Seismic Proving Test of Ultimate Piping Strength: Current Status of Preliminary Tests — II
Kenichi Suzuki, Y. Namita, H. Abe, I. Ichihashi, Kohei Suzuki, M. Ishiwata, T. Fujiwaka, H. Yokota
ICONE 2002; 573-580https://doi.org/10.1115/ICONE10-22225
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Topics: Pipes , Piping systems , Earthquake resistant design , Fatigue damage , Safety , Stress , Tensile strength
Seismic Proving Test of Eroded Piping: Program of Eroded Piping Tests
Y. Namita, K. Suzuki, H. Abe, I. Ichihashi, M. Shiratori, K. Iwata, N. Kojima, M. Ishiwata
ICONE 2002; 581-587https://doi.org/10.1115/ICONE10-22233
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Topics: Pipes
Analysis and Evaluation of the Liquefaction on Layered Soil
Sang Hoon Lee, Kwang Hoon Yoo
ICONE 2002; 589-593https://doi.org/10.1115/ICONE10-22251
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Topics: Liquefaction , Soil , Computer software , Nuclear power stations , Sands , Shear strength
Analysis and Insights About FE-Calculations of the EC-Forever-Experiments
H.-G. Willschuetz, E. Altstadt, F.-P. Weiss, B. R. Sehgal
ICONE 2002; 595-601https://doi.org/10.1115/ICONE10-22262
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Topics: Accidents , Automatic control , Convection , Cooling , Creep , Damage , Decision making , Failure , Finite element model , Floods
Fuel Assembly Nonlinear Dynamic Model
S. J. Shah, B. Brenneman
ICONE 2002; 603-608https://doi.org/10.1115/ICONE10-22269
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Topics: Dynamic models , Fuels , Manufacturing , Deflection , Stiffness , Displacement , Free vibrations , Seismic analysis , Springs , Stress
Analysis of a Defected Dissimilar Metal Weld in a PWR Power Plant
P. Efsing, J. Lagerstro¨m
ICONE 2002; 609-616https://doi.org/10.1115/ICONE10-22275
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Topics: Metals , Power stations , Pressurized water reactors , Safety , Fracture (Materials) , Boats , Inspection , Nozzles , Stress , Alloy steel
A Study on the Embedment Effect in the Soil-Structure Interaction Analysis of the APR1400
Young-Sun Jang, Kwang-Ho Joo, Chong-Hak Kim
ICONE 2002; 617-623https://doi.org/10.1115/ICONE10-22328
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Topics: Soil , Spectra (Spectroscopy) , Design , Nuclear power stations , Seismic analysis , Uncertainty
Integrated Analysis of Mechanical and Thermal Hydraulic Behavior of Graphite Stack in Channel-Type Reactors in Case of a Fuel Channel Rupture Accident
Sergei L. Soloviev, Boris A. Gabaraev, Leonid M. Parafilo, Dmitry V. Kruchkov, Oleg Yu. Novoselsky, Vladimir N. Filinov, Oleg I. Melikhov
ICONE 2002; 625-631https://doi.org/10.1115/ICONE10-22338
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Topics: Accidents , Fuels , Graphite , Pressure , Rupture
Seismic Behavior of Spent Fuel Dry Cask Storage Systems
Syed K. Shaukat, Vincent K. Luk
ICONE 2002; 633-638https://doi.org/10.1115/ICONE10-22395
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Topics: Spent nuclear fuels , Storage , Design , Soil , Concretes , Finite element analysis , Friction , Geometry , Rocks , Seismic analysis
Flow Induced Vibration and Fretting Wear in PWR Fuel
S. J. King, M. Y. Young, D. D. Seel, M. E. Conner, Roger Y. Lu, D. V. Paramonov
ICONE 2002; 639-648https://doi.org/10.1115/ICONE10-22399
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Topics: Flow-induced vibrations , Fuels , Pressurized water reactors , Wear , Fuel rods , Flow (Dynamics) , Excitation , Coolants , Geometry , High temperature
Passive and Active Vibration Control With Piezoelectric Fiber Composites
Yves Vigier, Amen Agbossou, Claude Richard
ICONE 2002; 657-663https://doi.org/10.1115/ICONE10-22434
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Topics: Composite materials , Fibers , Vibration control , Vibration , Circuits , Impedance (Electricity) , Computer simulation , Electrodes , Energy dissipation , Manufacturing
Results of Overpressurization Test of a 1:4-Scale Prestressed Concrete Containment Vessel Model
Michael F. Hessheimer, Satoru Shibata, James F. Costello
ICONE 2002; 665-672https://doi.org/10.1115/ICONE10-22455
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Topics: Containment vessels , Prestressed concrete , Containment , Pressurized water reactors , Accidents , Design , Displacement , Nuclear engineering , Pressure , Pressure testing
Evaluation of Pipe Whip Impacts on Neighboring Piping and Walls of the Ignalina Nuclear Power Plant
Gintautas Dundulis, Ronald F. Kulak, Algirdas Marchertas, Evaldas Narvydas, Mark C. Petry, Eugenijus Uspuras
ICONE 2002; 673-681https://doi.org/10.1115/ICONE10-22469
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Topics: Nuclear power stations , Pipes , Emergency core cooling systems , Accidents , Finite element analysis , Concrete walls , Coolants , Damage , Failure , Pipelines
Evaluation of Dynamic Behavior of Pile Foundations for Interim Storage Facilities Through Geotechnical Centrifuge Tests
Shizuo Tsurumaki, Hiroyuki Watanabe, Akira Tateishi, Kenichi Horikoshi, Shunichi Suzuki
ICONE 2002; 683-690https://doi.org/10.1115/ICONE10-22505
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Topics: Nuclear fuels , Pilings (Building) , Storage
Application of Seismic Isolation to the STAR-LM Reactor
B. Yoo, R. F. Kulak
ICONE 2002; 691-697https://doi.org/10.1115/ICONE10-22506
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Topics: Bearing design , Bearings , Coolants , Damping , Design , Industrial research , Liquid metals , Seismic analysis , Weight (Mass)
Improvement of the Damping Constants for Seismic Design of Piping System for NPP
Kei Kobayashi, Takashi Satoh, Nobuyuki Kojima, Kiyoshi Hattori, Masaki Nakagawa, Akihito Otani
ICONE 2002; 699-706https://doi.org/10.1115/ICONE10-22510
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Topics: Damping , Earthquake resistant design , Nuclear power stations , Piping systems , Pipes , Design , Collisions (Physics) , Friction , Deformation , Excitation
The Destructive High Pressure Tests of Cylindrical Shells
Yasumi Kitajima, Satoru Shibata
ICONE 2002; 707-714https://doi.org/10.1115/ICONE10-22528
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Topics: High pressure (Physics) , Pipes , Containment vessels , Failure , Finite element analysis , Pressure , Steel , Displacement , Prestressed concrete , Reinforced concrete
Seismic Re-Evaluation of the Armenian NPP Unit 2: Issues and Engineering Approach
Paruyr Zadoyan, Nikolaos Simos
ICONE 2002; 715-726https://doi.org/10.1115/ICONE10-22532
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Topics: Earthquake risk , Nuclear power stations , Soil , Spectra (Spectroscopy) , Design , Dynamic response , Generators , Nuclear power , Safety , Structures
Evaluation of Flow-Induced Vibration for Fixed Type Guide Rods of Shroud Head and Steam Dryer in ABWR
Shirou Takahashi, Hiroaki Tamako, Tsutomu Kawamura, Kouji Shiina, Masaaki Tsubaki, Akihiro Sakashita, Norimichi Yamashita, Tadashi Narabayashi, Tsuyoshi Hagiwara, Hideo Komita
ICONE 2002; 727-734https://doi.org/10.1115/ICONE10-22549
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Topics: Flow-induced vibrations , Nozzles , Rods , Steam
Large-Scale Parallel Finite Element Analysis of the Stress Singular Problems
Noriyuki Kushida, Hiroshi Okuda, Genki Yagawa
ICONE 2002; 735-740https://doi.org/10.1115/ICONE10-22562
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Topics: Finite element analysis , Stress , Gradient methods , Finite element methods , Relaxation (Physics)
Buckling Analysis in Creep Conditions: Review and Comparison
Andre´ Turbat, Bernard Drubay
ICONE 2002; 741-746https://doi.org/10.1115/ICONE10-22670
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Topics: Buckling , Creep , Design
Assessment of the Hydraulic Flows in the MARA8 Test-Facility Simulating a HCDA
M. F. Robbe, M. Lepareux
ICONE 2002; 747-758https://doi.org/10.1115/ICONE10-22687
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Topics: Accidents , Countermeasures , Evacuations , Flow (Dynamics) , Nuclear power stations , Safety , Test facilities
Assessment of the Mechanical Effects of a HCDA in a Simple Scale Model of a LMFBR
M. F. Robbe, M. Lepareux, Y. Cariou
ICONE 2002; 759-770https://doi.org/10.1115/ICONE10-22689
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Topics: Accidents , Countermeasures , Evacuations , Liquid metal fast breeder reactors , Mechanical properties , Nuclear power stations , Safety
Progress in the Development of J Estimation Schemes for the RSE-M Code
Patrick Le Delliou, Jean-Philippe Sermage, Pierre Cambefort, Bruno Barthelet, Philippe Gilles, Bruno Michel
ICONE 2002; 771-778https://doi.org/10.1115/ICONE10-22691
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Topics: In-service inspection , Pipes , Power stations , Pressure , Pressurized water reactors , Shells , Stress , Surface cracks , Torsion
Non-Linear Stress Analysis of Threaded Connection With High Strength Ratio Materials
K. R. Khair, P. N. Singh
ICONE 2002; 779-787https://doi.org/10.1115/ICONE10-22750
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Topics: ASME Standards , Collapse , Deformation , Design , Finite element analysis , Materials properties , Stress , Stress analysis (Engineering) , Thread
A Complete Piping Analysis With Thermal Stratification Loads
Milton Dong, Hong Ming Lee, Chii Chern
ICONE 2002; 789-796https://doi.org/10.1115/ICONE10-22763
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Topics: Pipes , Stress , Thermal stratification , Computer software , Fatigue damage , Piping systems , Design , Engineers , Failure , Modeling
Non-Linear Fluid-Structure Interaction in Cylindrical Shells
M. H. Toorani, A. A. Lakis
ICONE 2002; 797-808https://doi.org/10.1115/ICONE10-22776
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Topics: Anisotropy , Fluid structure interaction , Fluids , Pipes , Vibration
Main Steam Line Technical Design Improvement Using a More Detailed Piping Analysis
Zsolt Revesz
ICONE 2002; 809-813https://doi.org/10.1115/ICONE10-22783
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Topics: Design , Pipes , Steam , Stress , Earthquakes , Boiling water reactors , Hardware , Nuclear power stations , Piping systems , Structural elements (Construction)

License Renewal, Life Extension, Decommissioning and Decontamination

Progress in Decommissioning of Ignalina NPP Unit 1
Darius Ancius, Rimantas Krenevicius, Saulius Kutas, Michel Chouha
ICONE 2002; 815-822https://doi.org/10.1115/ICONE10-22057
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Topics: Nuclear decommissioning , Nuclear power stations , Safety , Licensing , Governments , Nuclear power , Engineering standards , Radioactive wastes , Resolution (Optics) , Waste management
Pipe Decontamination Involving “String-Foam Circulation”
J. P. Turchet, B. Fournel, G. Estienne
ICONE 2002; 823-834https://doi.org/10.1115/ICONE10-22118
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Topics: Decontamination , Pipes , String
Decontamination of Phebus Experimental Target Chamber Using Sprayed Foam
B. Fournel, S. Angot, P. Joyer
ICONE 2002; 835-844https://doi.org/10.1115/ICONE10-22119
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Topics: Decontamination , Aluminum alloys , Lasers , Pellet fusion
Estimation of a Decommissioning Program Considering the Reuse of Demolition Materials
Eiichi Sakata, Sachio Ozaki, Michihiko Hironaga, Daisuke Ogane, Tatsuo Usui, Yutaka Kono
ICONE 2002; 845-850https://doi.org/10.1115/ICONE10-22382
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Topics: Demolition , Expert systems , Nuclear decommissioning , Recycling
Application of Ozone Chemical Decontamination (T-OZON ) to the Equipment for Disposal
M. Enda, Y. Yaita, H. Sakai, H. Aoi, I. Inami, M. Nakagami, K. Kani
ICONE 2002; 851-855https://doi.org/10.1115/ICONE10-22430
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Topics: Decontamination
Shutdown and Closure of the Experimental Breeder Reactor–II
John A. Michelbacher, Carl E. Baily, Daniel K. Baird, S. Paul Henslee, Collin J. Knight, Kenneth E. Rosenberg
ICONE 2002; 857-865https://doi.org/10.1115/ICONE10-22462
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Topics: Breeder reactors , Carbon dioxide , Circuits , Design , Explosives , Fast neutron reactors , Heat , Hydrogen , Liquid metal fast breeder reactors , Liquid metals
EU Funded Research Activities on NPPs Operational Safety
P. Manolatos, G. Van Goethem
ICONE 2002; 867-874https://doi.org/10.1115/ICONE10-22484
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Topics: Nuclear power stations , Safety , Accident management , Life extension , Nuclear fission , Nuclear power , Nuclear reactor safety
Analysis of Piping Systems for Life Extension of Heavy Water Plants in India
Rajesh K. Mishra, R. S. Soni, H. S. Kushwaha, V. Venkat Raj
ICONE 2002; 875-881https://doi.org/10.1115/ICONE10-22516
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Topics: Life extension , Piping systems , Water , Stress , Corrosion , Clearances (Engineering) , Design , Fatigue , Thermal expansion , ASME Standards
A Proactive Aging/Asset Management Model to Optimize Equipment Maintenance Resources Over Plant Lifetime
Theodore A. Meyer, Robert K. Perdue, Joel Woodcock, G. Gary Elder
ICONE 2002; 883-892https://doi.org/10.1115/ICONE10-22537
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Topics: Maintenance , Optimization , Computer software , Decision making , Economic analysis , Energy generation , Nuclear industry , Nuclear power plant operations , Nuclear power stations , Pressurized water reactors
Development of Russian Regulatory Basis for License Renewal/Life Extension of Nuclear Power Plants
Jaroslav Pachner, Inna V. Kaliberda
ICONE 2002; 893-900https://doi.org/10.1115/ICONE10-22569
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Topics: Licensing , Life extension , Nuclear power stations , Service life (Equipment) , Engineering drawing and drafting , Safety
Generic Aging Management Programs for License Renewal of BWR Reactor Coolant System Components
V. N. Shah, Y. Y. Liu
ICONE 2002; 901-909https://doi.org/10.1115/ICONE10-22576
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Topics: Boiling water reactors , Licensing , Nuclear reactor coolants , Amperes , Pipes , Inspection , Reactor vessels , Acceptance criteria , Corrective actions , Cracking (Materials)
Robotics for Long-Term Monitoring
Sarkis Shahin, Celso Duran
ICONE 2002; 911-913https://doi.org/10.1115/ICONE10-22780
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Topics: Robotics , Sensors , Contamination , Data acquisition , Inspection , Computers , Containers , Governments , Hazardous substances , Imaging
Manually-Operated Crate Dismantlement System for Los Alamos National Laboratory
John Laffitte, Leo Lagos, Miguel Morales
ICONE 2002; 915-918https://doi.org/10.1115/ICONE10-22782
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Topics: Accidents , Cordage , Cutting , Decontamination , Fatigue , Glass reinforced plastics , Green technology , Hand tools , Hazardous substances , Hazards
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