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Proceedings Papers
Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation
Nuclear Safety, Security, and Cyber Security
Experimental Study of Radon Exhalation Rate in Uranium-Like Rock Based on Closed Chamber Method
ICONE 2018; V004T06A001https://doi.org/10.1115/ICONE26-81067
Topics:
Rocks
,
Uranium
,
Diffusion (Physics)
,
Errors
,
Leakage
,
Mining
,
Radiation (Physics)
,
Radioactivity
Noise Reduction Treatment and Analysis of Accumulated Radon Concentration in Uranium-Like Rock Based on Wavelet Theory
ICONE 2018; V004T06A002https://doi.org/10.1115/ICONE26-81068
Topics:
Noise control
,
Rocks
,
Uranium
,
Wavelets
,
Human factors
,
Instrumentation
,
Iron powders
,
Radiation (Physics)
,
Radioisotopes
,
Raw materials
Research on Source Inversion for Nuclear Accidents Based on Variational Data Assimilation With the Dispersion Model Error
ICONE 2018; V004T06A005https://doi.org/10.1115/ICONE26-81094
Topics:
Accidents
,
Errors
,
Emergency response
,
Contamination
,
Modeling
,
Nuclear power stations
,
Parallel processing
,
Wind tunnels
Nuclear Facility Safety Enhancement Using Sandia National Laboratories’ Computer Codes
ICONE 2018; V004T06A006https://doi.org/10.1115/ICONE26-81097
Topics:
Computers
,
Safety
,
Fire
,
Physics
,
Chemistry
,
Dynamics (Mechanics)
,
Fluid mechanics
,
Industrial research
,
Leakage
,
Nuclear power stations
Diffusion Law and Simulation Analysis of Radon in Uranium Tailings Based on Multiple Gauss Plume Model
ICONE 2018; V004T06A008https://doi.org/10.1115/ICONE26-81189
Topics:
Diffusion (Physics)
,
Plumes (Fluid dynamics)
,
Simulation analysis
,
Uranium
,
Wind velocity
,
Hazards
,
Pollution
,
Radiation (Physics)
,
Stability
High Efficient Detritiation Catalysts for Fusion Safety
ICONE 2018; V004T06A009https://doi.org/10.1115/ICONE26-81269
Topics:
Catalysts
,
Safety
,
Oxidation
,
Zirconium
,
Atoms
,
Metals
,
Methane
,
Absorption
,
Agglomeration (Materials)
,
Fusion reactors
Research on the Influence of Complex Terrain on Atmospheric Dispersion After Accident
ICONE 2018; V004T06A012https://doi.org/10.1115/ICONE26-81378
Topics:
Accidents
,
Computational fluid dynamics
,
Computer software
,
Emergencies
,
Evacuations
,
Flow (Dynamics)
,
Lakes
,
Modeling
,
Nuclear power stations
,
Nuclides
Development of Hydrogen Treatment System in Severe Accident: Part 5 — Effect of Steam Flow on Performance of a Hydrogen Treatment Unit With Metal Oxides
ICONE 2018; V004T06A013https://doi.org/10.1115/ICONE26-81386
Topics:
Accidents
,
Flow (Dynamics)
,
Hydrogen
,
Metals
,
Steam
,
Pipes
,
Temperature
,
Boiling water reactors
,
Containment vessels
,
Errors
Development of Experimental Technology for Simulated Fuel-Assembly Heating to Address Core-Material-Relocation Behavior During Severe Accident
ICONE 2018; V004T06A014https://doi.org/10.1115/ICONE26-81411
Topics:
Accidents
,
Fuels
,
Heating
,
Manufacturing
,
Melting
,
Plasmas (Ionized gases)
,
Blades
,
Computerized tomography
,
Electrons
,
Engineering prototypes
Facilities and Experience on Impact Test of Packages for Radioactive Materials Transport
Li Guoqiang, Zhuang Dajie, Wang Xuexin, Meng Dongyuan, Zhang Jiangang, Sun Hongchao, Sun Shutang, Ma Anping
ICONE 2018; V004T06A016https://doi.org/10.1115/ICONE26-81451
Topics:
Impact testing
,
Radioactive substances
,
Reinforced concrete
,
Steel
,
Accidents
,
Concretes
,
Construction
,
Cranes
,
Measuring instruments
,
Stress
Calculation of Core Damage Frequency Caused by Main Control Board Fire in the Main Control Room for Small Modular Reactors
ICONE 2018; V004T06A017https://doi.org/10.1115/ICONE26-81467
Topics:
Control panels
,
Control rooms
,
Damage
,
Fire
,
Small modular reactors
,
Cables
,
Computer software
,
Fire risk
,
Nuclear power stations
,
Safety
Safety Analysis Model of DUCG Based on FMEA/FTA
ICONE 2018; V004T06A018https://doi.org/10.1115/ICONE26-81484
A Critical Experimental Study of Bubble Effect in the Process of Spent Fuel Dissolving
ICONE 2018; V004T06A021https://doi.org/10.1115/ICONE26-81644
Topics:
Bubbles
,
Spent nuclear fuels
,
Nuclear fuels
,
Absorption
,
Fuels
,
Heat
,
Leakage
,
Neutrons
,
Safety
,
Simulation
The Design of a Nuclear Emergency Decision Deduction and Training Platform
ICONE 2018; V004T06A022https://doi.org/10.1115/ICONE26-81691
Topics:
Design
,
Emergencies
,
Simulation
,
Accidents
,
Emergency preparedness
,
Nuclear power stations
,
Security
,
China
,
Computer simulation
,
Computer software
Tritium Transport Characteristics Analysis in Molten Salt Reactor Under Transient Conditions
ICONE 2018; V004T06A023https://doi.org/10.1115/ICONE26-81728
Topics:
Molten salt reactors
,
Transients (Dynamics)
,
Absorption
,
Accidents
,
Corrosion
,
Dynamic response
,
Graphite
,
High temperature
,
Steady state
Development of Hydrogen Treatment System in Severe Accident: Part 4 — Study of Fission Products and Steam Effect on Hydrogen Treatment Characteristics
ICONE 2018; V004T06A024https://doi.org/10.1115/ICONE26-81759
Topics:
Accidents
,
Hydrogen
,
Nuclear fission
,
Steam
,
Vents
,
Boiling water reactors
,
Pressure
,
Manganese dioxide
,
Metals
,
Oxidation
Preliminary Hazard Analysis of Uranium Hexafluoride Accident
ICONE 2018; V004T06A030https://doi.org/10.1115/ICONE26-81956
Topics:
Accidents
,
Hazard analysis
,
Uranium
,
Risk
,
Emergencies
,
Hazards
,
Nuclear fuel cycle
LBLOCA Initiated Emergency Condition Analysis for a China Three-Loop PWR
ICONE 2018; V004T06A031https://doi.org/10.1115/ICONE26-81960
Topics:
China
,
Emergencies
,
Pressurized water reactors
,
Accidents
,
Failure
,
Feedwater
,
Fukushima nuclear disaster, Japan, 2011
,
Safety
,
Water
,
Boilers
Numerical Research on Shock Resistance Safety Analysis of Ship Power Plant Valve
ICONE 2018; V004T06A032https://doi.org/10.1115/ICONE26-82137
Topics:
Power stations
,
Safety
,
Ships
,
Shock (Mechanics)
,
Valves
,
Stress
,
Modal analysis
,
Stress concentration
,
ASME Standards
,
Emission spectroscopy
Tests of the Package for the Transport of Natural Uranium Hexafluoride
Sun Hongchao, Li Guoqiang, Zhuang Dajie, Sun Shutang, Meng Dongyuan, Lian Yiren, Chen Lei, Zhang Jiangang
ICONE 2018; V004T06A034https://doi.org/10.1115/ICONE26-82151
Topics:
Uranium
,
External pressure
,
Finite element analysis
,
Radioactive substances
,
Regulations
,
Structural analysis
,
Heat
,
Leakage
,
Safety
,
Testing
Research on the Passive Residual Heat Removal System of Floating Nuclear Plants
ICONE 2018; V004T06A035https://doi.org/10.1115/ICONE26-82219
Topics:
Heat
,
Nuclear power stations
,
Design
,
Accidents
,
Oceans
,
Ships
,
China
,
Computation
,
Cooling
,
Energy generation
Review and Security Assessment of Red Oil Explosions in Evaporator
Lian Yiren, Sun Hongchao, Chen Lei, Meng Dongyuan, Li Guoqiang, Zhuang Dajie, Sun Shutang, Zhang Jiangang
ICONE 2018; V004T06A036https://doi.org/10.1115/ICONE26-82221
Topics:
Explosions
,
Security
,
Nuclear fuels
,
Accidents
,
Chemical reactions
,
Explosives
Discussion About Sodium-Concrete Reaction in Presence of Internal Heater
ICONE 2018; V004T06A037https://doi.org/10.1115/ICONE26-82233
Topics:
Concretes
,
Sodium
,
Sodium fast reactors
,
Ablation (Vaporization technology)
,
Accidents
,
Aerosols
,
Chemical reactions
,
Containment vessels
,
Heating
,
Hydrogen
Research on the Neutron Multiplicity Pulse Trains Computer Simulation
ICONE 2018; V004T06A038https://doi.org/10.1115/ICONE26-82262
Topics:
Computer simulation
,
Neutrons
,
Trains
,
Simulation
,
Nondestructive evaluation
Development of Boron Dilution Model in COBRA-EN
ICONE 2018; V004T06A039https://doi.org/10.1115/ICONE26-82269
Topics:
Boron
,
Accidents
,
Coolants
,
Turbulent diffusion
,
Computational fluid dynamics
,
Computer software
,
Diffusion (Physics)
,
Fuels
,
Ignorance
,
Pressure
Segmented γ Scanning Device and its Experimental Research
ICONE 2018; V004T06A040https://doi.org/10.1115/ICONE26-82327
Online Adversarial Learning of Reactor State
ICONE 2018; V004T06A041https://doi.org/10.1115/ICONE26-82372
Topics:
Curve fitting
,
Design
,
Feedback
,
Fourier transforms
,
Instrumentation
,
Physics
Assessment of Control Room Radiological Habitability of High-Temperature Reactor Pebble-Bed Module in Shidao Bay Multi-Reactor Nuclear Power Site
ICONE 2018; V004T06A042https://doi.org/10.1115/ICONE26-82448
Topics:
Control rooms
,
High temperature
,
Nuclear power
,
Design
,
Accidents
,
China
,
Computational methods
,
Coolants
,
Licensing
,
Meteorology
Numerical Simulation of Debris Bed Relocation Behavior in Sodium-Cooled Fast Reactor
ICONE 2018; V004T06A044https://doi.org/10.1115/ICONE26-82493
Topics:
Computer simulation
,
Sodium fast reactors
,
Particulate matter
,
Shear strength
,
Fuels
,
Accidents
,
Boiling
,
Coolants
,
Cooling
,
Density
The Development of the Advanced Method for the Source Term Evaluation Applicable to the Dynamic PRA
ICONE 2018; V004T06A045https://doi.org/10.1115/ICONE26-82523
Topics:
Accidents
,
Containment
,
Evaluation methods
,
Nuclear fission
,
Nuclear power stations
,
Probabilistic risk assessment
,
Risk
,
Safety
,
Stress
Numerical Impact Simulation of Aircraft Into Reinforced Concrete Walls With Different Thickness
Kazuma Hirosaka, Hidekazu Takazawa, Katsumasa Miyazaki, Norihide Tohyama, Hiroyuki Nouji, Naomi Matsumoto
ICONE 2018; V004T06A047https://doi.org/10.1115/ICONE26-82616
Topics:
Aircraft
,
Reinforced concrete
,
Simulation
,
Phantoms
,
Concrete walls
,
Simulation models
,
Computer simulation
,
Damage
,
Impact testing
,
Kinematics
Computer Code Verification and Validation
Validation of Film Evaporation Model in GASFLOW-MPI
ICONE 2018; V004T15A003https://doi.org/10.1115/ICONE26-81249
Topics:
Evaporation
,
Containment
,
Heat
,
Wall temperature
,
Air flow
,
Computational fluid dynamics
,
Cooling systems
,
Heating
,
Nuclear power stations
,
Safety
Development and Validation of a Correlation for Wet Resuspension Simulation
ICONE 2018; V004T15A005https://doi.org/10.1115/ICONE26-81286
Topics:
Accident management
,
Accidents
,
Aerosols
,
Boiling
,
Bubbles
,
Circuits
,
Condensed matter
,
Containment
,
Coolants
,
Cooling
A Validation of RELAP on Predicting Nuclear Power Plant Phenomena
ICONE 2018; V004T15A006https://doi.org/10.1115/ICONE26-81424
Topics:
Nuclear power stations
,
Thermal stratification
,
Pipes
,
Surges
,
Computational fluid dynamics
,
Cooling
,
Errors
,
Feedwater
,
Junctions
,
Piping systems
Blind Simulations of NACIE-UP Experimental Tests by STH Codes
Nicola Forgione, Morena Angelucci, Gianluca Barone, Massimiliano Polidori, Antonio Cervone, Ivan Di Piazza, Fabio Giannetti, Pierdomenico Lorusso, Thorsten Hollands, Angel Papukchiev
ICONE 2018; V004T15A007https://doi.org/10.1115/ICONE26-81434
Topics:
Engineering simulation
,
Simulation
,
Computer simulation
,
Flow (Dynamics)
,
Liquid metals
,
Performance
,
Pressure
,
Temperature
,
Thermal hydraulics
Uncertainty Analysis of Power Distribution for NESTOR Based on the Double Latin Hypercube Sampling Method
Hongkuan Liao, Qing Li, Yingrui Yu, Yuying Hu, Lei Wu, Chenlin Wang, Jinyu Wang, Jinghui Wang, Peng Xiao
ICONE 2018; V004T15A008https://doi.org/10.1115/ICONE26-81441
Topics:
Sampling methods
,
Uncertainty analysis
,
Uncertainty
,
Nuclear design
,
Computer software
,
Approximation
,
Computation
,
Design
,
Economics
,
Modeling
OECD-NEA Expert Group on Multi-Physics Experimental Data, Benchmarks and Validation
Timothy Valentine, Kostadin Ivanov, Maria Avramova, Alessandro Petruzzi, Jean-Pascal Hudelot, Upendra Rohatgi, Kiril Velkov
ICONE 2018; V004T15A009https://doi.org/10.1115/ICONE26-81571
Topics:
Physics
,
Linkages
,
Modeling
,
Nuclear power
,
Simulation
,
Underpinning
Verification of Shielding Calculation Capability of RMC With H.B.Robinson-2 Pressure Vessel Benchmark
ICONE 2018; V004T15A010https://doi.org/10.1115/ICONE26-81694
Topics:
Pressure vessels
,
Computational methods
,
Neutron flux
,
Neutrons
,
Nuclear fission
,
Cavities
,
China
,
Neutron sources
,
Nuclear fuel cycle
,
Teams
Numerical Investigation of Corium Coolability in Core Catcher: Sensitivity to Modeling Parameters
ICONE 2018; V004T15A011https://doi.org/10.1115/ICONE26-81841
Topics:
Modeling
,
Simulation
,
Accidents
,
Vessels
,
Coolants
,
Fuels
,
Sodium
,
Sodium fast reactors
,
Fast neutron reactors
,
Fluid dynamics
QUENCH-06 Experiment Post-Test Calculations and Integrated Uncertainty Analysis With RELAP/SCDAPSIM/MOD3.4 and MOD3.5
ICONE 2018; V004T15A012https://doi.org/10.1115/ICONE26-81912
Topics:
Uncertainty analysis
,
Modeling
,
Heat losses
,
Internships
,
Uncertainty
,
Computer software
,
Contact resistance
,
Convection
,
Experimental analysis
,
Fuel rods
Assessment of Time and Space High-Order Schemes for Two-Fluid Seven-Equation Two-Pressure Model Using the Reversed Water Faucet Problem
ICONE 2018; V004T15A013https://doi.org/10.1115/ICONE26-81942
Topics:
Fluids
,
Pressure
,
Water
,
Gravity (Force)
,
Diffusion (Physics)
,
Flow (Dynamics)
,
Waves
,
Algorithms
,
Drag (Fluid dynamics)
,
Pressure gradient
Analysis Contour Plots in RELAP/SCDAPSIM/MOD 3.4 and MOD 4.1
ICONE 2018; V004T15A014https://doi.org/10.1115/ICONE26-81991
Topics:
Accidents
,
Blades
,
Boiling water reactors
,
Computer software
,
Fuel rods
,
Hydrogen production
,
Nuclear industry
,
Nuclear reactors
,
Rods
,
Simulation
Application of RELAP/SCDAPSIM/MOD4.1 to the Analysis of Advanced Reactor/Fluid Systems With Liquid Molten Salt in the Presence of Non-Condensable Gases
ICONE 2018; V004T15A015https://doi.org/10.1115/ICONE26-82041
Topics:
Fluids
,
Gases
,
Molten salt reactors
,
Design
,
Fuels
,
Liquid metals
,
Physics
A Simplified Numerical Benchmark for Pool-Type Sodium Fast Reactors
ICONE 2018; V004T15A018https://doi.org/10.1115/ICONE26-82260
Topics:
Sodium fast reactors
,
Physics
,
Modeling
,
Geometry
,
Neutrons
,
Simulation
,
Testing
,
Thermal hydraulics
Moving From V&V to V&V&C in Nuclear Thermal-Hydraulics
ICONE 2018; V004T15A019https://doi.org/10.1115/ICONE26-82574
Topics:
Density
,
Film boiling
,
Flow (Dynamics)
,
Heat flux
,
High pressure (Physics)
,
Nucleate boiling
,
Pipes
,
Power density
,
Pressure
,
Temperature
Simulation of JAERI Downcomer Effective Water Head Experiments With WCOBRA/TRAC-TF2
ICONE 2018; V004T15A020https://doi.org/10.1115/ICONE26-82610
Topics:
Simulation
,
Water
,
Superheating
,
Reactor vessels
,
Accidents
,
Pressurized water reactors
,
Test facilities
,
Transients (Dynamics)
,
Boiling
,
Coolants
Two Stage Data Driven V&V for an Agile Thermohydraulic Analysis Method
ICONE 2018; V004T15A021https://doi.org/10.1115/ICONE26-82628
Topics:
Architects
,
Boilers
,
Databases
,
Design
,
Dimensions
,
Engineering disciplines
,
Nuclear power stations
,
Nuclear reactors
,
Safety
,
Small modular reactors
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