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Proceedings Papers
Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications
Structural Integrity
A Comparative Parametric Study of Single Step and Double Step Swage Autofrettage in Swaged Metal Tubes
ICONE 2009; 11-16https://doi.org/10.1115/ICONE17-75081
Topics:
Autofrettage
,
Metals
,
Computer software
,
Finite element analysis
,
Computer programming
,
Design
,
Cylinders
,
Diesel engines
,
Failure
,
Fatigue life
Investigation of Discrepancies in Waterhammer Structural Integrity Analysis Simulation and Actual Vibration Testing
ICONE 2009; 17-28https://doi.org/10.1115/ICONE17-75100
Topics:
Simulation
,
Testing
,
Vibration
,
Pipes
,
Displacement
,
Friction
,
Stress
,
ASME Standards
,
Simulation results
,
Damping
Reactor Vessel Closure Head Drop Analysis: Sensitivity Study on the Effects of Representing Nonlinear Behavior in the Closure Head Assembly
ICONE 2009; 29-36https://doi.org/10.1115/ICONE17-75170
Topics:
Manufacturing
,
Reactor vessels
,
Failure
,
Nuclear power stations
,
Cranes
,
Cavities
,
Cooling systems
,
Deflection
,
Deformation
,
Missiles
Use of Shear Lugs for Anchorage to Concrete
ICONE 2009; 37-44https://doi.org/10.1115/ICONE17-75175
Topics:
Anchorage
,
Concretes
,
Shear (Mechanics)
,
Design
,
Design methodology
,
Nuclear power stations
,
Stress
,
Construction
,
Nuclear construction
,
Structural design
Design by Analysis of Waste Packages at Yucca Mountain for Impact Loads
ICONE 2009; 101-111https://doi.org/10.1115/ICONE17-75355
Topics:
Design
,
Stress
,
Radioactive wastes
,
Collisions (Physics)
,
Containers
,
Containment
,
Earthquakes
,
Engineering simulation
,
Rocks
,
Shells
Evaluation of the Isolation System Influence in the Seismic Loading Analysis Applied to a Near Term Deployment Reactor
ICONE 2009; 143-151https://doi.org/10.1115/ICONE17-75459
Topics:
Dampers
,
Design
,
Earthquake risk
,
Earthquakes
,
Energy dissipation
,
Finite element analysis
,
Nuclear power stations
,
Nuclear reactors
,
Safety
,
Seismic analysis
Nonlinear Analyses for Thermal Cracking in the Design of Concrete Structures
ICONE 2009; 153-160https://doi.org/10.1115/ICONE17-75474
Topics:
Concretes
,
Cracking (Materials)
,
Design
,
Fracture (Process)
,
Stress
,
Concrete cracking
,
Containment
,
Design methodology
,
Modeling
,
Reinforced concrete
Stress Classification Plane and Its Application in Finite Element Analysis
ICONE 2009; 171-179https://doi.org/10.1115/ICONE17-75547
Topics:
Finite element analysis
,
Stress
,
Design
,
Pressure vessels
,
Boilers
,
Cutting
,
Finite element model
,
Mechanical engineers
,
Membranes
,
Stress concentration
Friction Welding of Mild Steel Components
ICONE 2009; 197-204https://doi.org/10.1115/ICONE17-75649
Topics:
Friction welding
,
Mechanical testing
,
Steel
Wave Propagation Analysis of Piping Structures
ICONE 2009; 213-219https://doi.org/10.1115/ICONE17-75760
Topics:
Pipes
,
Wave propagation
,
Accidents
,
Modeling
,
Nuclear power stations
,
Piping systems
,
Timoshenko beam theory
,
Vibration
The Development of Impact Analysis Methodology for CEDM Missile of APR1400
ICONE 2009; 221-228https://doi.org/10.1115/ICONE17-75797
Topics:
Missiles
,
Flow (Dynamics)
,
Design
,
Nozzles
,
Earthquakes
,
Equilibrium (Physics)
,
Kinetic energy
,
Manufacturing
,
Reactor vessels
,
Structural response analysis
Review of Recent Aging-Related Degradation Occurrences of Structures and Passive Components in U.S. Nuclear Power Plants
ICONE 2009; 235-244https://doi.org/10.1115/ICONE17-75814
Topics:
Nuclear power stations
,
Anchorage
,
Computer software
,
Concretes
,
Containment
,
Filters
,
Nuclear power
,
Piping systems
,
Reactor vessels
,
Structural steel
Evaluation of Load-Time Functions Due to Impact of Soft Missiles
ICONE 2009; 245-252https://doi.org/10.1115/ICONE17-75825
Topics:
Missiles
,
Stress
,
Aircraft
,
Accelerometers
,
Computer simulation
,
Finite element analysis
,
Peak load
,
Pressure
,
Safety
,
Shapes
Engineering Practices for Tokamak Window Assemblies
ICONE 2009; 253-263https://doi.org/10.1115/ICONE17-75858
Topics:
Tokamaks
,
Design
,
Safety
,
Ceramics
,
Failure
,
Industrial ceramics
,
Nonmetallic materials
,
Plasmas (Ionized gases)
,
Brittleness
,
Containment
Sensitivity Investigation of Specimen Shape on Elastic Behaviour of Perforated Plate
ICONE 2009; 265-272https://doi.org/10.1115/ICONE17-75916
Topics:
Elasticity
,
Shapes
,
Compression
,
Finite element analysis
,
Computer software
,
Plates (structures)
,
Boilers
,
Elastic moduli
,
Poisson ratio
,
Preferences
Critical Velocity of Potential Flow in Interaction With a System of Plates
ICONE 2009; 281-289https://doi.org/10.1115/ICONE17-76059
Topics:
Flow (Dynamics)
,
Plates (structures)
,
Fluids
,
Displacement
,
Boundary-value problems
,
Equations of motion
,
Pressure
,
Stiffness
,
Damping
,
Dynamic response
Safety and Security
Modelling of Material Properties Influence in Fuel-Coolant Interaction Codes
ICONE 2009; 313-321https://doi.org/10.1115/ICONE17-75039
Topics:
Coolants
,
Fuels
,
Materials properties
,
Modeling
,
Drops
,
Explosions
,
Steam
,
Approximation
,
Cooling
,
Heat transfer
Validation of Calculated Skyshine Dose From Turbine Building by Using MCNP5 With Experimental Data at Shimane Nuclear Power Station
ICONE 2009; 355-359https://doi.org/10.1115/ICONE17-75145
Topics:
Nuclear power stations
,
Turbines
,
Structures
,
Boiling water reactors
,
Concretes
,
Radiation (Physics)
,
Roofs
Numerical Simulation of the Behavior of Fission Products in the Primary Circuit of the VVER During the LOCA Severe Accident
ICONE 2009; 361-367https://doi.org/10.1115/ICONE17-75159
Topics:
Accidents
,
Circuits
,
Computer simulation
,
Nuclear fission
,
Nuclear power stations
,
Evaporation
,
Aerosols
,
Condensation
,
Containment
,
Coolants
Vulnerability of Nuclear Power Plants to Voltage Sag Induced by Disturbances in the Transmission Grid: The Concept of Zone of Vulnerability for Voltage
ICONE 2009; 369-378https://doi.org/10.1115/ICONE17-75177
Topics:
Nuclear power stations
,
Safety
,
Buses
,
Diesel generators
,
Emergencies
,
Power grids
,
Risk
,
Security
,
Separation (Technology)
Verification of Modified SCDAP/RELAP5 Against CANDU Fuel Deformation Experimental Results
ICONE 2009; 379-385https://doi.org/10.1115/ICONE17-75196
Topics:
Deformation
,
Fuels
,
Accidents
,
Cooling
,
Flow (Dynamics)
,
Geometry
,
Hydrogen
,
Pressure
,
Solidification
,
Steam
Analytical Evaluation of Core Bowing Reactivity in the 4S Reactor
ICONE 2009; 403-411https://doi.org/10.1115/ICONE17-75223
Topics:
Absorption
,
Displacement
,
Fast neutron reactors
,
Feedback
,
Flow (Dynamics)
,
Neutrons
,
Optical mirrors
,
Sodium
Implementation of a Pressure Drop Model for the CFD Simulation of Clogged Containment Sump Strainers
Alexander Grahn, Eckhard Krepper, Frank-Peter Weiß, So¨ren Alt, Wolfgang Ka¨stner, Alexander Kratzsch, Rainer Hampel
ICONE 2009; 427-438https://doi.org/10.1115/ICONE17-75249
Topics:
Computational fluid dynamics
,
Containment
,
Pressure drop
,
Simulation
,
Fibers
,
Particulate matter
,
Porosity
,
Accidents
,
Compacting
,
Coolants
Evaluation of Monju Core Damage Risk With Change of AOT Using Probabilistic Method
ICONE 2009; 445-453https://doi.org/10.1115/ICONE17-75263
Topics:
Breeder reactors
,
Cooling
,
Damage
,
Engineering prototypes
,
Regulations
,
Risk
,
Safety
,
Sodium
A New Simulation Code for Analyzing Loss of Coolant Accidents in VVER-440/213 Reactors Concerning Activity Transport
Attila Madaras, Sa´ndor Deme, Zolta´n Ho´zer, Edit La´ng, Istva´n Ne´meth, Tama´s Pa´zma´ndi, Pe´ter Sza´nto´
ICONE 2009; 471-476https://doi.org/10.1115/ICONE17-75306
Topics:
Accidents
,
Alpha decay
,
Computers
,
Containment
,
Coolants
,
Design
,
Gas flow
,
Modeling
,
Nuclear fission
,
Nuclear power
On-Line Workload Assessment by the PET Method
ICONE 2009; 477-481https://doi.org/10.1115/ICONE17-75352
Topics:
Accidents
,
Containment
,
Human reliability analysis
,
NASA
,
Nuclear power stations
,
Performance evaluation
,
Rupture
,
Steam
Sources of Uncertainty in a Fire Probabilistic Safety Assessment
ICONE 2009; 483-486https://doi.org/10.1115/ICONE17-75360
Topics:
Fire
,
Probabilistic safety assessment
,
Uncertainty
,
Cables
,
Probability
,
Safety
,
Failure
,
Model development
,
Modeling
,
Nuclear power stations
Analysis and Characterization of Sequences in Atucha II PHWR
ICONE 2009; 487-494https://doi.org/10.1115/ICONE17-75364
Topics:
Heavy water reactors
,
Heat
,
Temperature
,
Safety
,
Boilers
,
Coolants
,
Design
,
Heat exchangers
,
Heat sinks
,
Inertia (Mechanics)
RELAP Model for Atucha II PHWR
M. Schivo, G. Bedrossian, J. Gonza´lez, P. Zanocco, M. Gime´nez, M. Caputo, P. Serrano, O. Mazzantini
ICONE 2009; 495-503https://doi.org/10.1115/ICONE17-75365
Topics:
Heavy water reactors
,
Construction
,
Design
,
Geometry
,
Licensing
,
Probabilistic safety assessment
,
Steady state
Safety Aspects of a PWR With an Inventive TRISO Fuel Particle Composition
ICONE 2009; 505-509https://doi.org/10.1115/ICONE17-75384
Topics:
Fuels
,
Heating
,
Particulate matter
,
Pressurized water reactors
,
Rods
,
Safety
ASTEC, COCOSYS, and LIRIC Interpretation of the Iodine Behaviour in the Large-Scale THAI Test Iod-9
ICONE 2009; 519-531https://doi.org/10.1115/ICONE17-75414
Topics:
Condensation
,
Desorption
,
Diffusion (Physics)
,
Domes (Structural elements)
,
Mass transfer
,
Modeling
,
Simulation results
,
Steel
,
Vessels
,
Water
Analysis of a BWR ATWS With Boron Injection
ICONE 2009; 541-549https://doi.org/10.1115/ICONE17-75455
Topics:
Boiling water reactors
,
Boron
,
Transients (Dynamics)
,
Computers
,
Feedwater
,
Safety
,
Scram
,
Simulation
Ex-Vessel Coolability Analysis for a Belgian NPP
ICONE 2009; 551-561https://doi.org/10.1115/ICONE17-75456
Topics:
Nuclear power stations
,
Vessels
,
Cooling
,
Accident management
,
Accidents
,
Cavities
,
Damage
,
Failure
,
Hardware
,
Thermomechanics
Approach for the Analysis of a Shutdown Scenario in the Framework of the Validation of Severe Accident Management Guidelines in Belgium
ICONE 2009; 563-573https://doi.org/10.1115/ICONE17-75457
Topics:
Accident management
,
Accidents
,
Coolants
,
Emergencies
,
Heat
,
Teams
,
Accounting
,
Boilers
,
Containment
,
Control rooms
Validation of Severe Accident Management Guidance in Belgium
ICONE 2009; 583-592https://doi.org/10.1115/ICONE17-75472
Topics:
Accident management
,
Safety
,
Accidents
,
Nuclear power stations
,
Feedback
,
Containment
,
Control rooms
,
Drills (Tools)
,
Sprays
,
Teams
Fire PRA Database Development and Applications
ICONE 2009; 593-599https://doi.org/10.1115/ICONE17-75517
Topics:
Databases
,
Fire
,
Nuclear power stations
,
Power stations
,
Probabilistic risk assessment
New Approach for Environmental Protection During Severe Accidents at Nuclear Power Plants
S. A. Kulyukhin, N. B. Mikheev, L. N. Falkovskii, L. A. Reshetov, M. Ya. Zvetkova, V. P. Osipov, I. V. Yagodkin, S. S. Skvortsov, V. M. Berkovich, G. S. Taranov, M. M. Grigor’ev, A. A. Noskov, M. I. Mitrofanov, V. M. Meshkov
ICONE 2009; 601-609https://doi.org/10.1115/ICONE17-75518
Topics:
Accidents
,
Nuclear power stations
,
Decontamination
,
Pressure
,
Sorption
,
Steam
,
Condensers (steam plant)
,
Containment
,
Ejectors
,
Filtration
Quantification of the RELAP5 Model Uncertainty for Application to the Loss-of-RHR Event During the Mid-Loop Operation
ICONE 2009; 611-621https://doi.org/10.1115/ICONE17-75550
Topics:
Uncertainty
,
Heat transfer
,
Condensation
,
Cooling
,
Flow (Dynamics)
,
Safety
,
Stratified flow
,
Water
,
Boilers
,
Boiling
Closed Model for Calculation of Differential Pressure After a Loss of Coolant Accident in Boiling Water Reactors
ICONE 2009; 623-628https://doi.org/10.1115/ICONE17-75562
Topics:
Accidents
,
Boiling water reactors
,
Coolants
,
Pressure
,
Containment
,
Heat
,
Insulation
,
Exhaust systems
,
Condensation
,
Cooling systems
Improvements in the German Fire PSA Methodology Demonstrated at a German BWR Built to Earlier Standards
ICONE 2009; 629-637https://doi.org/10.1115/ICONE17-75595
Topics:
Boiling water reactors
,
Fire
,
Nuclear power stations
,
Damage
,
Uncertainty
,
Cables
,
Circuits
,
Engineering simulation
,
Failure
,
Probabilistic safety assessment
Reliability Analysis by Multilevel Flow Models: A Qualitative Analysis Method and Its Application for FTA Validation
ICONE 2009; 639-648https://doi.org/10.1115/ICONE17-75681
Topics:
Event history analysis
,
Flow (Dynamics)
,
Safety
,
Algorithms
,
Modeling
,
Complex systems
,
Failure mechanisms
,
Reliability
A Bayesian Framework for Model Uncertainty Considerations in Fire Simulation Codes
ICONE 2009; 649-656https://doi.org/10.1115/ICONE17-75684
Topics:
Fire
,
Simulation
,
Uncertainty
,
Hazards
,
Chain
,
Chemical processes
,
Computers
,
Errors
,
Failure
,
Instrumentation
Lessons Learned and Insights From Implementation of EPRI Guidelines on Internal Flooding at Fort Calhoun Station
ICONE 2009; 677-683https://doi.org/10.1115/ICONE17-75805
Topics:
Floods
,
Fortification
,
Nuclear power stations
,
Risk
,
Combustion engineering
,
Failure
,
Maintenance
,
Optimization
,
Pipes
,
Probabilistic risk assessment
The Gasification of Graphite Matrix in Pebble Bed Reactors
ICONE 2009; 685-690https://doi.org/10.1115/ICONE17-75827
Topics:
Fuel gasification
,
Graphite
,
Fuels
,
Corrosion
,
Steam
,
Engineering simulation
,
Simulation
,
Very high temperature reactors
,
Coolants
,
Helium
Potential Ways to Modify the NRC Safety Goal Policy
ICONE 2009; 691-697https://doi.org/10.1115/ICONE17-75852
Topics:
Safety
,
Nuclear reactors
,
Risk
,
Damage
,
Electric power generation
Lessons Learned in Reviewing CCF Events
ICONE 2009; 713-717https://doi.org/10.1115/ICONE17-75887
Experimental Investigation of Non-Condensable Gases Effect on Novovoronezh NPP-2 Steam Generator Condensation Power Under the Condition of Passive Safety Systems Operation
ICONE 2009; 735-743https://doi.org/10.1115/ICONE17-75942
Topics:
Boilers
,
Condensation
,
Gases
,
Nuclear power stations
,
Safety
,
Steam
,
Heat
,
Test facilities
,
Circuits
,
Flow (Dynamics)
Point Lepreau Refurbishment Project Level 2 PSA Applications
L. Comanescu, S. Sawh, M. Wei, B. Lee, A. Petrescu, A. Nainer, R. K. Jaitly, A. F. Jean, D. F. Basque, D. S. Mullin
ICONE 2009; 751-756https://doi.org/10.1115/ICONE17-75972
Topics:
Accidents
,
Damage
,
Design
,
Failure
,
Fire
,
Floods
,
Maintenance
,
Power stations
,
Probabilistic safety assessment
,
Risk
Westinghouse AP1000 Solution to Long-Term Cooling Debris Concerns
ICONE 2009; 757-764https://doi.org/10.1115/ICONE17-76026
Topics:
Cooling
,
Containment
,
Accidents
,
Design
,
Pressurized water reactors
,
Coolants
,
Safety
,
Particulate matter
,
Testing
,
Construction
ACR-1000™ Level 1 PSA Summary
U. Menon, S. Aprodu, R. Bettig, R. Henderson, T. Ha, P. Iliescu, B. Karimi, M. El-Mansi, J. Robinson, K. Torabi, E. Eman, J. Wu, P. Santamaura
ICONE 2009; 785-791https://doi.org/10.1115/ICONE17-76048
Topics:
Accidents
,
Boilers
,
Containment
,
Containment systems
,
Coolants
,
Cooling systems
,
Damage
,
Design
,
Earthquakes
,
Economics
Advanced Applications of Nuclear Technology
Analysis for Digital Pulse Waveform Based on Cd (Zn) Te Detector
ICONE 2009; 793-797https://doi.org/10.1115/ICONE17-75052
Topics:
Sensors
,
Signal processing
Allegro: The European Gas Fast Reactor Demonstrator Project
Christian Poette, Vale´rie Brun-Magaud, Franck Morin, Jean-Franc¸ois Pignatel, Richard Stainsby, Konstantin Mikityuk
ICONE 2009; 815-822https://doi.org/10.1115/ICONE17-75326
Topics:
Fast neutron reactors
,
Design
,
Ceramics
,
Fuels
,
Neutrons
,
Nuclear reactors
,
High temperature
,
Safety
,
Accidents
,
Circuits
Development of a New Monte-Carlo Treatment Planning System for Boron Neutron Capture Therapy
ICONE 2009; 823-829https://doi.org/10.1115/ICONE17-75407
Topics:
Boron
,
Dosimetry
,
Neutrons
,
Patient treatment
,
Particulate matter
,
Radiation therapy
,
Protons
,
Accuracy and precision
,
Computation
,
Ions
Test Results From the Idaho National Laboratory 15kW High Temperature Electrolysis Test Facility
ICONE 2009; 831-841https://doi.org/10.1115/ICONE17-75417
Topics:
High temperature steam
,
Test facilities
,
High temperature
,
Hydrogen
,
Design
,
Heat
,
Feedstock
,
Heating
,
Hydrogen production
,
Solid oxide fuel cells
The 30 MeV Proton Beam Emittance Measurement via a Designed and Constructed Wire Scanner and Using WinAGILE Beam Transport Code
ICONE 2009; 843-846https://doi.org/10.1115/ICONE17-75434
Topics:
Proton beams
,
Wire
,
Cyclotrons
,
Patient treatment
,
Position control
,
Protons
,
Sensors
,
Stepper motors
Current Status and Performance of the J-PARC Accelerators
ICONE 2009; 857-866https://doi.org/10.1115/ICONE17-75557
Topics:
Ceramics
,
Construction
,
Density
,
Design
,
Downtime
,
Ducts
,
Eddies (Fluid dynamics)
,
Eddy currents (Electricity)
,
Electromagnets
,
Life sciences
The Coupling of Nuclear Heat and Hydrogen Production Thermochemical Cycles
ICONE 2009; 875-883https://doi.org/10.1115/ICONE17-75702
Topics:
Cycles
,
Heat
,
Hydrogen production
,
Water
Evolving Innovative Reactor Design: Putting the I Into R&D
ICONE 2009; 891-895https://doi.org/10.1115/ICONE17-75811
Topics:
Design
,
Supercritical water reactors
,
Cycles
,
China
,
Collaboration
,
Fuels
,
Heat
,
Hydrogen production
,
Innovation
,
Metals
Advanced Application of BNCT in Advanced Cancers
ICONE 2009; 905-914https://doi.org/10.1115/ICONE17-75906
Topics:
Cancer
,
Boron
,
Tumors
,
Lung
,
Biological tissues
,
Neutrons
,
Patient treatment
,
Computerized tomography
,
Design
,
Irradiation (Radiation exposure)
Optimization of Dead-Layer Thickness for a HPGe Detector Using UCODE-MCNP Codes
ICONE 2009; 923-929https://doi.org/10.1115/ICONE17-75939
Topics:
Optimization
,
Sensors
,
Crystals
,
Building materials
,
Calibration
,
Modeling
,
Simulation
,
Statistics
Why Massive Nuclear Deployment is Essential
ICONE 2009; 931-935https://doi.org/10.1115/ICONE17-75949
Topics:
Carbon capture and storage
,
Carbon dioxide
,
Climate change
,
Cycles
,
Density
,
Disasters
,
Emissions
,
Energy generation
,
Geothermal engineering
,
Governments
Balance of Plant for Nuclear Applications
STP Balance of Plant Model Update Experience and Results
ICONE 2009; 945-953https://doi.org/10.1115/ICONE17-75006
Topics:
Computer software
,
Damage
,
Financial risk
,
Modeling
,
Probabilistic risk assessment
,
Profitability
,
Reliability
,
Risk
,
Risk analysis
,
Risk management
Equipment Reliability Based Ageing and Lifetime Management for Asco´ and Vandello´s Nuclear Power Plants
ICONE 2009; 965-973https://doi.org/10.1115/ICONE17-75406
Topics:
Nuclear power stations
,
Reliability
,
Public utilities
,
Safety
,
Design
,
Engines
,
Life extension
,
Maintenance
,
Motors
,
Service life (Equipment)
Electrical Network Modeling and Electrical Transfer Simulation of C.N. Asco´ I and C.N. Asco´ II, to Obtain Voltage and Frequency Limit Values Allowing the Electrical Transfer From the Main Generator to the External 110 kV Power Grid
ICONE 2009; 993-1002https://doi.org/10.1115/ICONE17-75546
Topics:
Generators
,
Modeling
,
Power grids
,
Simulation
,
Circuit breakers
,
Delays
,
Design
,
Electronic systems
,
Nuclear power stations
,
Nuclear reactor coolants
Simplified Approach to Establishing Bounding Main Steam Piping Support Load Increase Due to Reactor Power Uprate
ICONE 2009; 1011-1019https://doi.org/10.1115/ICONE17-75743
Topics:
Pipes
,
Power uprate
,
Steam
,
Stress
,
Flow (Dynamics)
,
Fluids
,
Turbines
,
Valves
,
Electric power generation
,
Engineers
Study on Pipe Wastage Mechanism by Liquid Droplet Impingement Erosion
Yuma Higashi, Tadashi Narabayashi, Yoichiro Shimazu, Masashi Tsuji, Syuichi Ohmori, Michitsugu Mori, Kenichi Tezuka
ICONE 2009; 1021-1027https://doi.org/10.1115/ICONE17-76029
Topics:
Drops
,
Erosion
,
Pipes
,
Corners (Structural elements)
,
Corrosion
,
Errors
,
Flow (Dynamics)
,
Mass measurement
,
Microscopes
,
Nuclear power stations