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Proceedings Papers
Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management
Plant Systems, Structures, Components, and Materials
Filtration Technology Research of Graphite Dust Produced in Spent Fuel Transportation Process in HTR-PM
ICONE 2018; V002T03A001https://doi.org/10.1115/ICONE26-81022
Topics:
Dust
,
Filtration
,
Graphite
,
Spent nuclear fuels
,
Transportation systems
,
Fuels
,
Gas cooled reactors
,
High temperature
,
Nuclear power
,
Pipelines
Analytical Study on Fragility Evaluation With Uncertainty Against Fault Displacement for Nuclear Power Plant Buildings
ICONE 2018; V002T03A002https://doi.org/10.1115/ICONE26-81072
Topics:
Displacement
,
Nuclear power stations
,
Structures
,
Uncertainty
,
Soil
,
Hazards
,
Accidents
,
Building materials
,
Chaos
,
Design
A Recommended Method for SC Wall Design-Evaluation Regarding the Elasto-Plastic Behavior Under Beyond Design Basis Seismic Loading
ICONE 2018; V002T03A003https://doi.org/10.1115/ICONE26-81088
Topics:
Design
,
Composite materials
,
Concretes
,
Steel
,
Constitutive equations
,
Shear (Mechanics)
,
Construction
,
Nuclear power stations
,
Plates (structures)
,
Stress
The Influence of Thermal Deformation on the Dynamic Characteristics of AMB Rotor of HTR-PM Helium Blower
ICONE 2018; V002T03A004https://doi.org/10.1115/ICONE26-81132
Topics:
Helium
,
Rotors
,
Thermal deformation
,
Temperature
,
Bearings
,
Computer simulation
,
Damping
,
Displacement
,
Electromagnetic force
,
Engines
A Structural Integrity Assessment of a Nuclear Boiler Superheater Bifurcation at High Temperature
ICONE 2018; V002T03A005https://doi.org/10.1115/ICONE26-81167
Topics:
Bifurcation
,
Boilers
,
High temperature
,
Superheaters
,
Creep
,
Metals
,
Fatigue
,
Fracture (Materials)
,
Safety
,
Boiler tubes
Experimental Study of Motion-Resistance Force of Hydraulic Cylinder of CRHDM
ICONE 2018; V002T03A006https://doi.org/10.1115/ICONE26-81214
Topics:
Hydraulic cylinders
,
Cylinders
,
Friction
,
Leakage
,
Carbon
,
Design
,
Diamonds
,
Hydraulic control
,
Hydraulic drive systems
,
Intellectual property
Design of the Important Area Airborne Radioactivity Monitoring System and Calculation of the Alarm Threshold of HTR-PM
ICONE 2018; V002T03A007https://doi.org/10.1115/ICONE26-81232
Topics:
Design
,
Monitoring systems
,
Radioactivity
,
Pressurized water reactors
,
Coolants
,
Radiation measurement
,
Emergencies
,
Feedback
,
Gases
,
Helium
Research on Structural Design and Analysis of S-CO2 Turbine Impeller
ICONE 2018; V002T03A008https://doi.org/10.1115/ICONE26-81267
Topics:
Impellers
,
Structural design
,
Supercritical carbon dioxide
,
Turbines
,
Deformation
,
Stress
,
Safety
,
Blades
,
Brayton cycle
,
Carbon
Study on Methods for HCLPF Value of Nonlinear Supports System of Steam Generator
ICONE 2018; V002T03A010https://doi.org/10.1115/ICONE26-81279
Topics:
Boilers
,
Failure
,
Probability
,
Stress
,
Nonlinear systems
,
Nuclear reactor coolants
,
Plasticity
,
Safety
,
Seismic analysis
,
Stress analysis (Engineering)
Experimental Study and Analysis of the Deformable Pipe of CRHDM
ICONE 2018; V002T03A011https://doi.org/10.1115/ICONE26-81281
Topics:
Pipes
,
Hydraulic cylinders
,
Design
,
Hydraulic control
,
Hydraulic drive systems
,
Intellectual property
,
Patents
Research on Auxiliary Bearing Structure With Buffer Shim Based on LS-DYNA for Helium Circulator of HTR-10
ICONE 2018; V002T03A013https://doi.org/10.1115/ICONE26-81304
Topics:
Bearings
,
Helium
,
Polishing equipment
,
Rotors
,
Stress
,
Damage
,
Stress concentration
,
Computer software
,
Deformation
,
Finite element methods
Influence Factors on Moisture Absorption Process of Carbon Material in HTGR
ICONE 2018; V002T03A016https://doi.org/10.1115/ICONE26-81412
Topics:
Absorption
,
Carbon
,
Very high temperature reactors
,
Boron
,
Corrosion
,
Diffusion (Physics)
,
Graphite
,
High temperature
,
Temperature
A Systematic Study of the Material Performance of Hot Isostatically Pressed Type 316L Stainless Steel Powder for the Civil Nuclear Sector
ICONE 2018; V002T03A017https://doi.org/10.1115/ICONE26-81438
Topics:
Stainless steel
,
Manufacturing
,
Materials properties
,
Oxygen
,
ASTM International
,
Collaboration
,
Cycles
,
Defense industry
,
Electricity (Physics)
,
Hot pressing
Eulerian Two-Fluid Model for Aerosol Removal in Filtered Containment Venting Scrubbers
ICONE 2018; V002T03A018https://doi.org/10.1115/ICONE26-81506
Topics:
Aerosols
,
Containment
,
Fluids
,
Particulate matter
,
Drops
,
Water
,
Computers
,
Drag (Fluid dynamics)
,
Flow (Dynamics)
,
Matlab
Research on Simplified Method of Transients Combining and Loading in Fatigue Crack Growth Analysis of Carbon Steel Nuclear Piping
ICONE 2018; V002T03A019https://doi.org/10.1115/ICONE26-81640
Topics:
Carbon steel
,
Fatigue cracks
,
Pipes
,
Transients (Dynamics)
,
Fracture (Materials)
,
Stress
,
ASME Standards
,
Fatigue
Design of the Sampling Measurement and Radiochemistry Lab in the Nuclear Island of HTR-PM
ICONE 2018; V002T03A020https://doi.org/10.1115/ICONE26-81701
Topics:
Design
,
Instrumentation
,
Regulations
,
Coolants
,
Dust
,
Germanium
,
Helium
,
Nuclear power stations
,
Radiation measurement
,
Radiation measuring instruments
Optimal Design and Performance Simulation of a Novel Semi-Active Vibration Absorber for Pipeline System of NPP
ICONE 2018; V002T03A021https://doi.org/10.1115/ICONE26-81741
Topics:
Design
,
Nuclear power stations
,
Pipeline systems
,
Simulation
,
Vibration absorbers
,
Vibration
,
Excitation
,
Pipelines
,
Stiffness
,
Absorption
Welded Joint Evaluation for Chromium Controlled Carbon Steel Piping to Improve FAC Resistance
ICONE 2018; V002T03A022https://doi.org/10.1115/ICONE26-81913
Topics:
Carbon steel
,
Pipes
,
Welded joints
,
Welding
,
Alloy steel
,
Alloys
,
Condensed matter
,
Construction
,
Corrosion
,
Feedwater
Research of γ-Ray 3D Scanning Detection and Analysis System
ICONE 2018; V002T03A023https://doi.org/10.1115/ICONE26-81929
Study on the Mechanism and Characteristics of Transient Noise of the Steam Discharge Pipes
ICONE 2018; V002T03A024https://doi.org/10.1115/ICONE26-81938
Topics:
Noise (Sound)
,
Pipes
,
Steam
,
Transients (Dynamics)
,
Valves
,
Flow (Dynamics)
,
Collapse
,
Energy dissipation
,
Friction
,
High pressure (Physics)
Residual Stress Measurement of Sealing Glass Based on Optical Fiber Sensing Technology
ICONE 2018; V002T03A027https://doi.org/10.1115/ICONE26-82135
Topics:
Glass
,
Optical fiber
,
Sealing (Process)
,
Stress
,
Metals
,
Fiber Bragg gratings
,
Containment
,
Diffraction gratings
,
Fiber optic sensors
,
Finite element model
Demonstrative HEAF (High Energy Arcing Fault) Fire Tests of High and Low Voltage Switchgears of Nuclear Power Plants
ICONE 2018; V002T03A028https://doi.org/10.1115/ICONE26-82177
Topics:
Fire testing
,
Nuclear power stations
,
Fire
,
Damage
,
Cables
,
Circuit breakers
,
Circuits
,
Copper
,
Design
,
Earthquakes
LBB Analysis on Nuclear-Class Pipes of Floating Nuclear Power Stations
ICONE 2018; V002T03A029https://doi.org/10.1115/ICONE26-82180
Topics:
Nuclear power stations
,
Pipes
,
Fracture (Materials)
,
Leakage
,
Design
,
Drilling
,
Fatigue
,
Finite element methods
,
Fracture mechanics
,
Leak-before-break
Experimental Research on the Fluid Induced Forces of Clearance Flow in Canned Motor Reactor Coolant Pump
ICONE 2018; V002T03A030https://doi.org/10.1115/ICONE26-82296
Topics:
Clearances (Engineering)
,
Engines
,
Flow (Dynamics)
,
Fluids
,
Motors
,
Nuclear reactor coolants
,
Pumps
,
Coolants
,
Stiffness
,
Boundary-value problems
Proposal of a Simple Evaluation Method for Sloshing Impact Pressure on Flat Roofs
ICONE 2018; V002T03A031https://doi.org/10.1115/ICONE26-82562
Topics:
Evaluation methods
,
Pressure
,
Roofs
,
Sloshing
,
Computational fluid dynamics
,
Damage
,
Earthquakes
,
Fast neutron reactors
,
Reactor vessels
,
Slabs
Evaluation of Local Damage to Reinforced Concrete Panels Subjected to Oblique Impact of Rigid and Soft Missiles
ICONE 2018; V002T03A034https://doi.org/10.1115/ICONE26-82615
Topics:
Damage
,
Missiles
,
Reinforced concrete
,
Impact testing
,
Simulation results
,
Simulation
,
Simulation analysis
,
Stiffness
Development of a Crack Opening Displacement Assessment Procedure Considering Change of Compliance at a Crack Part in Thin Wall Pipes Made of Modified 9Cr-1Mo Steel
ICONE 2018; V002T03A035https://doi.org/10.1115/ICONE26-82619
Topics:
Displacement
,
Fracture (Materials)
,
Pipes
,
Steel
,
Thin wall structures
,
Leakage
,
Sodium fast reactors
,
Sodium
,
Work hardening
,
Coolants
Transient Analysis of Fire Protection System at a Nuclear Power Plant Using Computer Code USLAM
ICONE 2018; V002T03A036https://doi.org/10.1115/ICONE26-82622
Topics:
Computers
,
Fire
,
Nuclear power stations
,
Transient analysis
,
Water hammer
,
Vacuum
,
Elevations (Drawings)
,
Valves
,
Water
,
Atmospheric pressure
WATCH Loop Development and Commissioning Tests
ICONE 2018; V002T03A037https://doi.org/10.1115/ICONE26-82626
Topics:
Boiling water reactors
,
Cladding systems (Building)
,
Corrosion
,
Design
,
Electricity (Physics)
,
Failure
,
Flow (Dynamics)
,
Fuel rods
,
Fuels
,
Heat flux
Structural Dynamic Transient Analysis of Fire Protection System at a Nuclear Power Plant
ICONE 2018; V002T03A038https://doi.org/10.1115/ICONE26-82627
Topics:
Fire
,
Nuclear power stations
,
Structural dynamics
,
Transient analysis
,
Stress
,
Pipeline risers
,
Piping systems
,
Risers (Casting)
,
Pipes
,
Water hammer
Risk Assessments and Management
Probabilistic Analysis of Creep-Induced SGTR for NPP
ICONE 2018; V002T14A001https://doi.org/10.1115/ICONE26-81032
Topics:
Creep
,
Nuclear power stations
,
Accidents
,
Probability
,
Accident management
,
Boilers
,
Failure
,
Pipes
,
Pressure
,
Probabilistic safety assessment
Level 1 PRA for External Vessel Storage Tank of Japan Sodium-Cooled Fast Reactor in Scheduled Refueling
ICONE 2018; V002T14A002https://doi.org/10.1115/ICONE26-81079
Topics:
Sodium fast reactors
,
Storage tanks
,
Vessels
,
Failure
,
Accidents
,
Sodium
,
Fuels
,
Damage
,
Dampers
,
Design
Evaluation of Core Damage Frequency of High Flux Engineering Test Reactor From Internal Events
ICONE 2018; V002T14A006https://doi.org/10.1115/ICONE26-81176
Topics:
Damage
,
Construction
,
Design
,
Safety
,
Computer software
,
Coolants
,
Modeling
,
Nuclear reactors
,
Reliability
,
System failures
Study on Shutdown Fire PRA for Nuclear Power Plant
ICONE 2018; V002T14A007https://doi.org/10.1115/ICONE26-81272
Topics:
Fire
,
Nuclear power stations
,
Risk
,
China
,
Damage
,
Fire prevention
,
Fire risk
,
Ignition
,
Probabilistic risk assessment
,
Shorelines
Dynamic Fault Tree Analysis Based on Dynamic Uncertain Causality Graph
ICONE 2018; V002T14A010https://doi.org/10.1115/ICONE26-81636
Topics:
Algorithms
,
Analytical methods
,
Chain
,
Cycles
,
Dynamics (Mechanics)
,
Explosions
,
Software development
,
Uncertainty
A PSA Case Study: Promoting the Reliability of the CRSS on the CMRR Through the ATWS Mitigation System
ICONE 2018; V002T14A011https://doi.org/10.1115/ICONE26-81755
Topics:
Reliability
,
Safety
,
China
,
Damage
,
Design
,
Failure
,
Probability
,
Rods
,
Scram
,
Transients (Dynamics)
Upgrade of Accident Sequence Model of PRA for LOCA Inside PCV
ICONE 2018; V002T14A015https://doi.org/10.1115/ICONE26-81959
Topics:
Accidents
,
Nozzles
,
Steam
,
Water
,
Pipes
,
Risk
,
Failure
,
Instrumentation
,
Nuclear power stations
,
Safety
Development of Fuel Route/Dropped Load PSA for UK ABWR
ICONE 2018; V002T14A016https://doi.org/10.1115/ICONE26-82022
Topics:
Fuels
,
Stress
,
Design
,
Spent nuclear fuels
,
Boiling water reactors
,
Construction equipment
,
Cranes
,
Failure
,
Machinery
,
Probabilistic safety assessment
Study on PRA Procedure Considering Combination of Multiple Events Using DQFM Methodology
ICONE 2018; V002T14A018https://doi.org/10.1115/ICONE26-82086
Topics:
Accidents
,
Earthquakes
,
Failure
,
Fire
,
Floods
,
Fukushima nuclear disaster, Japan, 2011
,
Nuclear power stations
,
Pipes
,
Safety
,
Simulation
Discussion of Issues for Small Modular Reactor PSA
ICONE 2018; V002T14A020https://doi.org/10.1115/ICONE26-82157
Real-Time Online Risk Monitoring and Management Method for Maintenance Optimization in Nuclear Power Plant
Anqi Xu, Zhijian Zhang, HuaZhi Zhang, Min Zhang, He Wang, Yingfei Ma, Sijuan Chen, Yan Wang, Gangyang Zheng
ICONE 2018; V002T14A021https://doi.org/10.1115/ICONE26-82472
Topics:
Maintenance
,
Nuclear power stations
,
Optimization
,
Risk monitoring
,
Risk
,
Risk assessment
,
Errors
,
Modeling
,
Computational methods
,
Control systems
Overview of PSA for the UK ABWR Generic Design Assessment
ICONE 2018; V002T14A023https://doi.org/10.1115/ICONE26-82553
Topics:
Design
,
Risk
,
Safety
,
Boiling water reactors
,
Damage
,
Model development
,
Probabilistic safety assessment
System Safety Analysis Method Based on Real-Time Online Risk Monitoring Technology
ICONE 2018; V002T14A024https://doi.org/10.1115/ICONE26-82563
Topics:
Risk monitoring
,
Safety
,
Risk
,
Nuclear power stations
,
Design
,
Optimization
,
Pumps
,
Signals