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Proceedings Papers
Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors
Operations and Maintenance, Aging Management and Plant Upgrades
Experimental Investigation of Static Characteristics of Swing and Tilting Disc Check Valves
ICONE 2016; V001T01A001https://doi.org/10.1115/ICONE24-60031
Topics:
Disks
,
Valves
,
Flow (Dynamics)
,
Fluid-dynamic forces
,
Pressure
,
Water
ASME Operation and Maintenance (OM) Code Overview
ICONE 2016; V001T01A002https://doi.org/10.1115/ICONE24-60086
Instrument Health Monitoring for Extending Calibration Intervals of Safety Related Instruments
ICONE 2016; V001T01A003https://doi.org/10.1115/ICONE24-60102
Topics:
Calibration
,
Instrumentation
,
Safety
,
Damage
,
Errors
,
Nuclear power stations
,
Testing
,
Maintenance
,
Reliability
,
Risk
Testing the Impact on Emergency Diesel Performance of Water in Diesel Fuel
ICONE 2016; V001T01A004https://doi.org/10.1115/ICONE24-60214
Topics:
Diesel
,
Emergencies
,
Testing
,
Water
,
Diesel engines
,
Engines
,
Computer software
,
Contamination
,
Nuclear power stations
,
Simulation
The Application of an Integrated Head Assembly for Advanced Power Reactor 1400
ICONE 2016; V001T01A009https://doi.org/10.1115/ICONE24-60860
Topics:
Manufacturing
,
Design
,
Cables
,
Nuclear power stations
,
Reactor vessels
,
China
,
Containment buildings
,
Cooling
,
Ducts
,
Fans
Non-Invasive On-Line Monitoring for Nuclear Power Plants Using Guided Waves Propagating in Steel Pipes With Different Types of Structural Complexity
ICONE 2016; V001T01A010https://doi.org/10.1115/ICONE24-60885
Topics:
Nuclear power stations
,
Pipes
,
Steel
,
Waves
,
Failure
,
In-service inspection
,
Inspection
,
Life extension
,
Radiation (Physics)
,
Robustness
Use of FEA Software in Evaluating Pump Vibration and Potential Remedial Actions to Abate Resonance in Industrial Vertical Pump/Motor Combinations
ICONE 2016; V001T01A011https://doi.org/10.1115/ICONE24-60890
Topics:
Computer software
,
Engines
,
Finite element analysis
,
Motors
,
Pumps
,
Resonance
,
Vibration
,
Screws
,
Electric motors
,
Generators
Uncertainty Assessment of Component Degradation Model Based on Support Vector Regression
ICONE 2016; V001T01A012https://doi.org/10.1115/ICONE24-61114
Topics:
Support vector machines
,
Uncertainty
,
Modeling
,
Nuclear power stations
,
Algorithms
,
Carbon steel
,
In-service inspection
,
Maintenance
,
Pipes
,
Sampling methods
Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory
Electron Beam Weldability of AA6061-T6 Aluminum Straps for U-Mo Follower Fuel Assembly Manufacturing
ICONE 2016; V001T02A002https://doi.org/10.1115/ICONE24-60041
Topics:
Aluminum
,
Cathode ray oscilloscopes
,
Electron beams
,
Fuels
,
Manufacturing
,
Exploding wires
,
Die cutting
,
Fillers (Materials)
,
Shearing (Deformation)
,
Welding
Comparative Study of Coated Particle Stresses With Different Coating Layer Performance
ICONE 2016; V001T02A003https://doi.org/10.1115/ICONE24-60046
Topics:
Coating processes
,
Coatings
,
Particulate matter
,
Stress
,
Fuels
,
Creep
,
Design
,
Irradiation (Radiation exposure)
,
Pressure
,
Shrinkage (Materials)
Preliminary Investigation of Physical Characteristics in a New Power Ramp Test Irradiation Rig
ICONE 2016; V001T02A004https://doi.org/10.1115/ICONE24-60052
Topics:
Irradiation (Radiation exposure)
,
Fuel rods
,
Fuels
,
Neutrons
,
Pressure
,
Computational methods
,
Curve fitting
,
Density
,
Heat
,
Neutron flux
The Preliminary Performance Study of ATF With M3 Fuel and Zr-4 Cladding
ICONE 2016; V001T02A011https://doi.org/10.1115/ICONE24-60150
Topics:
Cladding systems (Building)
,
Fuels
,
Zirconium
,
Accidents
,
Carbon
,
Coating processes
,
Coatings
,
Design
,
Failure
,
Failure mechanisms
Development of Plenum Temperature Model for Accident Analysis
ICONE 2016; V001T02A014https://doi.org/10.1115/ICONE24-60330
Topics:
Accidents
,
Temperature
,
Fuels
,
Heat transfer
,
Light water reactors
,
Computer software
,
Design
,
Fuel rods
,
Pressure
,
Resolution (Optics)
Measurements of Fine Structures in the Lead-Bismuth Eutectic Alloy Melts by Differential Scanning Calorimetry
ICONE 2016; V001T02A016https://doi.org/10.1115/ICONE24-60338
Topics:
Differential scanning calorimetry
,
Eutectic alloys
,
Alloys
,
Signals
,
Embrittlement
,
Melting point
,
Steel
,
Temperature
,
Generation IV reactors
,
Melting
Development and Application of the 3-D Core Fuel Management Transport Program for HFETR
ICONE 2016; V001T02A017https://doi.org/10.1115/ICONE24-60365
Topics:
Fuel management
,
Computational methods
,
Approximation
,
Errors
,
Geometry
,
Manufacturing
,
Neutron flux
,
Pressurized water reactors
,
Simulation
Transient Physics Procedure and Preliminary Characteristics Analysis of Aqueous Homogeneous Reactor
ICONE 2016; V001T02A018https://doi.org/10.1115/ICONE24-60372
Topics:
Physics
,
Transients (Dynamics)
,
Fuels
,
Approximation
,
Biomedicine
,
Bubbles
,
Design
,
Feedback
,
Geometry
,
Isotopes
MOCUM Code Verification and Sensibility Study Using C5G7 Benchmark
ICONE 2016; V001T02A020https://doi.org/10.1115/ICONE24-60443
Topics:
Errors
,
Geometry
,
Manufacturing
,
Neutron flux
,
Screw threads
,
Simulation
,
Thread
Analysis and Prospect of the Duplex Fuel Pellets of LOWI Type for Water-Cooled Reactors
ICONE 2016; V001T02A021https://doi.org/10.1115/ICONE24-60505
Topics:
Fuels
,
Water
,
Design
,
Manufacturing
,
Nuclear fuels
,
Power density
,
Temperature
,
Annulus
,
Cutting
,
Geometry
The Powerful MOC Module in Advanced Neutronics Lattice Code GALAXY
ICONE 2016; V001T02A025https://doi.org/10.1115/ICONE24-60661
Topics:
Boundary-value problems
,
China
,
Computation
,
Geometry
,
Neutrons
,
Nuclear power
,
Shapes
,
Trajectories (Physics)
A Three-Dimensional Flux Expansion Nodal Method for Hexagonal Geometry Application
ICONE 2016; V001T02A030https://doi.org/10.1115/ICONE24-61135
Topics:
Geometry
,
Currents
,
Diffusion (Physics)
,
Eigenvalues
,
Flux (Metallurgy)
,
Neutrons
,
Polynomials
Plant Systems, Structures, Components and Materials
Creep Assessment of Large Size High Temperature Components Using Small Creep Test Specimens
ICONE 2016; V001T03A001https://doi.org/10.1115/ICONE24-60010
Topics:
Creep
,
High temperature
,
Stress
,
Temperature
,
Damage
,
Design
,
Failure
,
High temperature materials
,
Nuclear power stations
,
Pipes
The Application of PSHA Method in the Determination of Beyond Design Basis Earthquake for New NPP Design
ICONE 2016; V001T03A002https://doi.org/10.1115/ICONE24-60043
Topics:
Design
,
Earthquakes
,
Nuclear power stations
,
Economics
,
Engineering design
,
Engineering design processes
,
Modeling
,
Nuclear engineering
,
Regulations
,
Safety
Design of the Spent Fuel Storage Well of HTR-PM
ICONE 2016; V001T03A003https://doi.org/10.1115/ICONE24-60051
Topics:
Design
,
Spent fuel storage
,
Spent nuclear fuels
,
Storage
,
Fuels
,
Safety
,
Wells
,
Heat
,
Accidents
,
High temperature
Thermodynamic Performance Analysis of Megawatts Portable Nuclear Power System Based on Regenerative Brayton Cycle
ICONE 2016; V001T03A004https://doi.org/10.1115/ICONE24-60081
Topics:
Brayton cycle
,
Nuclear power
,
Compression
,
Temperature
,
Cycles
,
Design
,
Compressors
,
Fuels
,
Heat
,
Matlab
Structural Integrity Research for Reactor Pressure Vessel Under In-Vessel Retention of a Core Melt
ICONE 2016; V001T03A005https://doi.org/10.1115/ICONE24-60092
Topics:
Reactor vessels
,
Vessels
,
Finite element analysis
,
Creep
,
Materials properties
,
Nuclear power stations
,
Pressure
,
Accidents
,
Leakage
,
Load bearing capacity
New Structure Design for SCWR Internal Components
ICONE 2016; V001T03A006https://doi.org/10.1115/ICONE24-60111
Nuclear Systems for a Low Carbon Electrical Grid
ICONE 2016; V001T03A007https://doi.org/10.1115/ICONE24-60128
Topics:
Carbon
,
Power grids
,
Hydrogen
,
Co-firing
,
Combined cycles
,
Electric power generation
,
Gas turbines
,
Nuclear power stations
,
Renewable energy
,
Storage
AP1000® Submergence Testing of Service Level I Protective Coatings
ICONE 2016; V001T03A012https://doi.org/10.1115/ICONE24-60228
Topics:
Protective coatings
,
Testing
,
Coatings
,
Containment
,
Temperature
,
Accidents
,
Coolants
,
Design
,
Fluids
,
Pressure
Fault Diagnosis of Feedwater Pump in Nuclear Power Plants Using Parameter-Optimized Support Vector Machine
ICONE 2016; V001T03A013https://doi.org/10.1115/ICONE24-60334
Topics:
Fault diagnosis
,
Feedwater
,
Nuclear power stations
,
Pumps
,
Support vector machines
,
Circuits
,
Condition monitoring
,
Signals
,
Vibration
Effect of Bolt Clamping Force and Constraint Arrangement on Structural Strength of Bolted Joint
ICONE 2016; V001T03A014https://doi.org/10.1115/ICONE24-60409
Topics:
Bolted joints
,
Computer simulation
,
Deformation
,
Finite element methods
,
Plates (structures)
,
Failure mechanisms
,
Friction
,
Hardware
,
Shear stress
,
Simulation
First-Principles Study of Atomic Hydrogen and Oxygen Adsorption on Doped-Iron Nanoclusters
ICONE 2016; V001T03A015https://doi.org/10.1115/ICONE24-60516
Topics:
Hydrogen
,
Iron
,
Oxygen
,
Zirconium
,
Metals
,
Atoms
,
Alloys
,
Clusters (Chemistry)
,
Density functional theory
,
Electron configuration
Establishing a Construction Method of an Automatic Fire Suppression System for Cable Tray Fires
ICONE 2016; V001T03A016https://doi.org/10.1115/ICONE24-60599
Topics:
Cables
,
Construction
,
Fire
,
Bubbles
,
Circuit breakers
,
Circuits
,
Cooling
,
Countermeasures
,
Electricity (Physics)
,
Failure
Numerical Simulation of Fretting Wear of Heat-Transfer Tubes in Steam Generator Under Random Excitation Forces
ICONE 2016; V001T03A017https://doi.org/10.1115/ICONE24-60630
Topics:
Boilers
,
Computer simulation
,
Heat transfer
,
Random excitation
,
Wear
,
Displacement
,
Finite element methods
,
Finite element model
,
Fluids
,
Friction
3D Linear Bifurcation Analysis of Steel Containment Vessel
ICONE 2016; V001T03A018https://doi.org/10.1115/ICONE24-60673
Topics:
Bifurcation
,
Containment vessels
,
Steel
,
Shells
,
Stability
,
Buckling
,
Containment
,
Stress
,
ASME Boiler and Pressure Vessel Code
,
ASME Standards
Study on Differences in Floor Response Spectra due to the Seismic Input Approach
ICONE 2016; V001T03A020https://doi.org/10.1115/ICONE24-60703
Topics:
Spectra (Spectroscopy)
,
Soil
,
Wave propagation
,
Rocks
Effect of Soil Structure Interaction on the Seismic Fragility of a Nuclear Reactor Building
ICONE 2016; V001T03A021https://doi.org/10.1115/ICONE24-60714
Topics:
Nuclear reactors
,
Soil
,
Safety
,
Earthquake risk
,
Earthquakes
,
Damage
,
Design
,
Nuclear power stations
,
Accounting
,
Chaos
Fracture Resistance of Cast Austenitic Stainless Steels
ICONE 2016; V001T03A022https://doi.org/10.1115/ICONE24-60736
Vortexing and Air Withdrawal Evaluations for Storage Tanks Using Physical Hydraulic Model Studies
ICONE 2016; V001T03A023https://doi.org/10.1115/ICONE24-60768
Topics:
Storage tanks
,
Flow (Dynamics)
,
Pumps
,
Water
,
Density
,
Design
,
Emergencies
,
Engineers
,
Fluids
,
Nozzles
Design of SC Walls and Connections in Nuclear Facilities
ICONE 2016; V001T03A029https://doi.org/10.1115/ICONE24-60962
Topics:
Design
,
Nuclear power stations
,
Steel
,
Failure
,
Quality control
,
Shear (Mechanics)
,
Stress
,
Wall panels
,
Accidents
,
Buckling
Design of Heat-Pipe Heat Exchanger (HPHE) for a Coal-to-Liquid Fuel Process Using Nuclear Energy
ICONE 2016; V001T03A030https://doi.org/10.1115/ICONE24-60994
Topics:
Coal
,
Design
,
Fuels
,
Heat exchangers
,
Heat pipes
,
Nuclear power
,
Heat
,
Boilers
,
Renewable energy
,
Steam
Design of the Process and Effluent Radiation Monitoring System of HTR-PM
ICONE 2016; V001T03A031https://doi.org/10.1115/ICONE24-61008
Topics:
Design
,
Radiation measurement
,
Pressurized water reactors
,
Very high temperature reactors
,
Carbon
,
Coolants
,
Dust
,
Fuels
,
Helium
,
Nuclear fission
Integrity Assessment of Mechanical Components Subjected to Mixed Mode Cracking
ICONE 2016; V001T03A032https://doi.org/10.1115/ICONE24-61097
Topics:
Fracture (Process)
,
Fracture (Materials)
,
Pipes
,
Failure
,
Finite element analysis
,
Metals
,
Nuclear power
,
Stress
,
Tension
A Study of Axial Compression in the ASME B&PV Code for Pipe Supports and Restraints
ICONE 2016; V001T03A033https://doi.org/10.1115/ICONE24-61101
Topics:
Compression
,
Pipes
,
Stress
,
ASME Boiler and Pressure Vessel Code
,
Buckling
,
Design
,
ASME Standards
,
Elastic analysis
,
Mechanical engineers
,
Stability
HIPed Hard Facings for Nuclear Applications: Materials, Key Potential Defects and Mitigating Quality Control Measures
ICONE 2016; V001T03A034https://doi.org/10.1115/ICONE24-61106
Topics:
Foundry coatings
,
Quality control
,
Hardening
,
Wear
,
Erosion
,
Stress
,
Cobalt
,
Contamination
,
Corrosion resistance
,
Crack propagation
Predictive Methods in the Assessment of Alloy 600 PWSCC Failures in Operating Pressurized Water Reactors
ICONE 2016; V001T03A037https://doi.org/10.1115/ICONE24-61141
Topics:
Alloys
,
Failure
,
Pressurized water reactors
,
Manufacturing
,
Base metals
,
Grain size
,
Indium alloys
,
Residual stresses
,
Stress
,
Temperature
On Experimental Simulation of Passive Evaporation-and-Condensation Systems of Reactor Thermal Shielding
Alexander N. Gershuni, Alexander P. Nishchik, Evgeviy N. Pis’mennyi, Victor G. Razumovskiy, Igor L. Pioro
ICONE 2016; V001T03A038https://doi.org/10.1115/ICONE24-61159
Topics:
Condensation
,
Evaporation
,
Heat shielding
,
Simulation
,
Heat
,
Cooling
,
Heat pipes
,
Reliability
,
Safety
,
Vapors
I&C, Digital Controls, and Influence of Human Factors
Electronics for Instrumentation and Controls in Accelerator Driven Sub-Critical System
ICONE 2016; V001T04A004https://doi.org/10.1115/ICONE24-60082
Topics:
Electronics
,
Instrumentation
,
Neutrons
,
Redundancy (Engineering)
,
Reliability
,
Errors
,
Heavy metals
,
Nuclear industry
,
Protons
,
Radiation damage
Parameter Optimization for AP1000 Steam Generator Feedwater Control System Using Particle Swarm Optimization Algorithm
ICONE 2016; V001T04A006https://doi.org/10.1115/ICONE24-60148
Topics:
Algorithms
,
Boilers
,
Control systems
,
Feedwater
,
Optimization
,
Particle swarm optimization
,
Nuclear power stations
,
Simulation
,
Water
,
Control equipment
Water Level Control for Steam Generator in Nuclear Power Based on Port-Controlled Hamiltonian Method
ICONE 2016; V001T04A007https://doi.org/10.1115/ICONE24-60274
Topics:
Boilers
,
Nuclear power
,
Water
,
Control modeling
,
Control equipment
,
Control systems
,
Energy dissipation
,
Equilibrium (Physics)
,
Modeling
,
Process control
Control Policy for Shared Objects in HTR-PM: Toward the Collision and Deadlock Avoidance
ICONE 2016; V001T04A008https://doi.org/10.1115/ICONE24-60406
Topics:
Collisions (Physics)
,
Design
,
Nuclear power stations
,
Turbines
,
Very high temperature reactors
,
Control systems
,
Delays
,
Fuels
,
Steam turbines
Program of Human-Machine Interface Verification and Validation of HTR-PM in China
ICONE 2016; V001T04A010https://doi.org/10.1115/ICONE24-60483
Topics:
China
,
Construction
,
Design
,
Gas cooled reactors
,
High temperature
,
Machinery
,
Steam
,
Steam turbines
Testing and Reliability Modelling of Safety Software for Digital Reactor Protection System of HTR-PM
ICONE 2016; V001T04A011https://doi.org/10.1115/ICONE24-60535
Topics:
Computer software
,
Modeling
,
Reactor protection systems
,
Reliability
,
Safety
,
Testing
,
Nuclear power stations
,
Event history analysis
,
China
,
Data mining
Assessment on an Intelligent Controller of Marine Condenser
ICONE 2016; V001T04A012https://doi.org/10.1115/ICONE24-60657
Topics:
Condensers (steam plant)
,
Intelligent control systems
,
Water
,
Cooling
,
Steam
,
Vacuum
,
Supercooling
,
Condensed matter
,
Control systems
,
Temperature
Intelligent Plant Configuration Management Using Wireless Sensors
ICONE 2016; V001T04A014https://doi.org/10.1115/ICONE24-60815
Topics:
Sensors
,
Nuclear power stations
,
Safety
,
Engineering prototypes
,
Errors
,
Hazards
,
Radiation (Physics)
,
Surveillance
,
Construction
,
Control systems
Development and Testing of Fault-Diagnosis Algorithms for Reactor Plant Systems
ICONE 2016; V001T04A018https://doi.org/10.1115/ICONE24-61024
Topics:
Algorithms
,
Fault diagnosis
,
Testing
,
Sensors
,
Computer software
,
Pressurized water reactors
,
Chain
,
Collaboration
,
Computer simulation
,
Control systems
Predictive Modeling of Acoustic Signals From Thermoacoustic Power Sensors (TAPS)
Christopher M. Dumm, Jeffrey S. Vipperman, Jorge V. Carvajal, Melissa M. Walter, Luke Czerniak, Amy S. Ruane, Paolo Ferroni, Michael D. Heibel
ICONE 2016; V001T04A019https://doi.org/10.1115/ICONE24-61034
Topics:
Acoustics
,
Modeling
,
Sensors
,
Signals
,
Waves
,
Instrumentation
,
Nuclear fission
,
Nuclear reactors
,
Radiation (Physics)
,
Sodium