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Proceedings Papers
Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events
Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management
Proven Technologies for the Solidification of Complex Liquid Radioactive Waste (LRW): Global Case Studies of Applications and Disposal Options
ICONE 2017; V007T10A002https://doi.org/10.1115/ICONE25-66081
Topics:
Radioactive wastes
,
Solidification
,
Nuclear power stations
,
Hazards
,
Isotopes
,
Nuclear decommissioning
,
Polymers
,
Storage
,
Warfare
Research on Approval of Domestic and International Transport Container Application of Radioactive Material
ICONE 2017; V007T10A004https://doi.org/10.1115/ICONE25-66279
Topics:
Containers
,
Radioactive substances
,
Safety
,
Licensing
,
China
,
Radiation (Physics)
,
Regulations
,
Commercial air transport
,
Design
,
Manufacturing
Study on Purification of U Scraps in Continuous Countercurrent Extractor
ICONE 2017; V007T10A005https://doi.org/10.1115/ICONE25-66336
Topics:
Raw materials
,
Reynolds number
,
Rotation
,
Uranium
Generation and Distribution of Tritium in HTGRs and Review on the Tritiated Water Treatment Technologies
ICONE 2017; V007T10A006https://doi.org/10.1115/ICONE25-66417
Topics:
Very high temperature reactors
,
Water treatment
,
Nuclear power stations
,
Water
,
Graphite
,
Lithium
,
Boron
,
Bricks
,
Carbon
,
Coolants
Application of Monte-Carlo Simulation to Design of Sampler and Detector in Radiation Monitoring System
Kei Sugihara, Hirotaka Sakai, Kanako Hattori, Genki Tanaka, Mitsunobu Hayashi, Toshiaki Ito, Naotaka Oda
ICONE 2017; V007T10A009https://doi.org/10.1115/ICONE25-66445
Topics:
Design
,
Radiation measurement
,
Sensors
,
Simulation
,
Modeling
,
Beta particles
,
Nuclides
,
Radiation (Physics)
,
Radioactive substances
Radiation Shielding Analysis of a Spent Fuel Dry Storage Cask for FA300 Spent Fuel Assemblies
ICONE 2017; V007T10A010https://doi.org/10.1115/ICONE25-66462
Topics:
Radiation (Physics)
,
Spent nuclear fuels
,
Storage
,
Ventilation
,
Concretes
,
Cavities
,
Cooling
,
Design
,
Design methodology
,
Fuels
Accident Safety Evaluation Method for Spent Fuel Dry Storage Facilities
ICONE 2017; V007T10A011https://doi.org/10.1115/ICONE25-66508
Topics:
Accidents
,
Evaluation methods
,
Safety
,
Spent nuclear fuels
,
Storage
,
Design
,
Heat
,
Nuclear power stations
,
Pressure
Comparison Research on Different Aerosol Pool Scrubbing Models
ICONE 2017; V007T10A012https://doi.org/10.1115/ICONE25-66540
Topics:
Aerosols
,
Boundary-value problems
,
Containment
,
Decontamination
,
Gas flow
,
Spent nuclear fuels
,
Steam
,
Temperature
Multi-Nuclide Separation Using Different Types of Zeolites
ICONE 2017; V007T10A015https://doi.org/10.1115/ICONE25-66611
Analysis on Radioactive Gas Movement and Delay Status Before Release
ICONE 2017; V007T10A017https://doi.org/10.1115/ICONE25-66713
Topics:
Delays
,
Activated carbon
,
Design
,
Dimensions
,
Flow (Dynamics)
,
Computational methods
,
Design methodology
,
Isotopes
,
Nuclear fission
,
Nuclear power stations
Analysis of Primary Coolant Corrosion Product Effect on Solid Waste Source Term
ICONE 2017; V007T10A018https://doi.org/10.1115/ICONE25-66945
Topics:
Coolants
,
Corrosion
,
Solid wastes
,
Filters
,
Design
,
Hydrogen
,
Nuclear power stations
,
Nuclides
,
Particulate matter
,
Radiation (Physics)
Technology Development on Reactor Dismantling and Investigation of Contamination in FUGEN
Goro Soejima, Hiroki Iwai, Yasuyuki Nakamura, Hirokazu Hayashi, Haruhiko Kadowaki, Hiroyuki Mizui, Kazuya Sano
ICONE 2017; V007T10A019https://doi.org/10.1115/ICONE25-66950
Topics:
Contamination
,
Technology development
,
Laser cutting
,
Cutting
,
Nuclear decommissioning
,
Water
,
Pipes
,
Zirconium alloys
,
Aluminum
,
Boiling
The Evaluation Method of Uranium Hexafluoride Leakage Accident Release Source Term
ICONE 2017; V007T10A022https://doi.org/10.1115/ICONE25-67143
Topics:
Accidents
,
Evaluation methods
,
Leakage
,
Uranium
,
Chemical properties
,
Diffusion (Physics)
,
Fuels
,
Nuclear fuels
TMSR Fuel Cycle Evaluation Under a Screening and Decision-Making Framework
Wu Jian-hui, Chen Jin-gen, Cai Xiang-zhou, Yu Cheng-gang, Zou Chun-yan, Jia Guo-bin, Li Xiao-xiao, Han Jian-long
ICONE 2017; V007T10A024https://doi.org/10.1115/ICONE25-67283
Topics:
Decision making
,
Nuclear fuel cycle
,
Fuels
,
Molten salt reactors
,
Nuclear fission
,
Nuclear power
,
Nuclear reactors
A Prototype of Tomographic Gamma Scanner
ICONE 2017; V007T10A026https://doi.org/10.1115/ICONE25-67372
Tungsten Powder Filled Polymers for Flexible Radiation Shields in Nuclear Industries
ICONE 2017; V007T10A027https://doi.org/10.1115/ICONE25-67382
Topics:
Filled polymers
,
Nuclear industry
,
Radiation (Physics)
,
Tungsten
,
Pipes
,
Composite materials
,
Density
,
Mechanical properties
,
Polymers
,
Shapes
Analysis and Application of Trace H2 and CH4 in Cycling Process Gas of Fusion Reactors by Gas Chromatography
ICONE 2017; V007T10A028https://doi.org/10.1115/ICONE25-67522
Topics:
Fusion reactors
,
Gas chromatography
,
Methane
,
Hydrogen
,
Flow (Dynamics)
,
Helium
,
Ionization
,
Pumps
,
Sensors
,
Temperature
Research Progress of Red Oil Explosion Accidents in Nuclear Fuel Reprocessing Plant
ICONE 2017; V007T10A029https://doi.org/10.1115/ICONE25-67554
Topics:
Accidents
,
Explosions
,
Nuclear fuels
,
Temperature
,
Safety
,
Construction
,
Contamination
,
Damage
,
Defense industry
,
Heavy metals
HEPA Filter Clogging and Volatile Material Release Under Solvent Fire Accident in Fuel Reprocessing Facility
ICONE 2017; V007T10A030https://doi.org/10.1115/ICONE25-67626
Topics:
Accidents
,
Fire
,
Fuels
,
HEPA filters
,
Countermeasures
,
Aerosols
,
Combustion
,
Pressure
,
Air filters
,
Design
Radiation Shielding Analysis of Radioactive Material Product Container
ICONE 2017; V007T10A032https://doi.org/10.1115/ICONE25-67673
Topics:
Containers
,
Radiation (Physics)
,
Radioactive substances
,
Nuclides
,
Beta particles
,
Neutrons
,
Alpha particles
,
Gamma rays
,
Nuclear fuels
,
Radiation effects
Research on the Reliability of Digital Instrumentation and Control System of Nuclear Power Plant Based on Dynamic Flowgraph Methodology
ICONE 2017; V007T10A034https://doi.org/10.1115/ICONE25-67719
Topics:
Control systems
,
Instrumentation
,
Nuclear power stations
,
Reliability
,
Design for Manufacturing
,
Modeling
,
Computer software
,
Failure
,
Hardware
,
Probability
Single Event Effect Characteristics Analysis of Typical Circuit Elements in Spacecraft Power Systems
ICONE 2017; V007T10A035https://doi.org/10.1115/ICONE25-67728
Topics:
Circuits
,
Power systems (Machinery)
,
Space vehicles
,
Transients (Dynamics)
,
Gates (Closures)
,
Modeling
,
Simulation
,
Capacitance
,
Chain
,
Computer simulation
Impact of Switching Time Interval for Dual Intakes on Workers in Main Control Room During Accidents
ICONE 2017; V007T10A037https://doi.org/10.1115/ICONE25-67742
Topics:
Accidents
,
Control rooms
,
Contamination
,
Instrumentation
,
Meteorology
,
Ventilation
,
Containment
,
Leakage
,
Radioactive substances
,
Relief valves
Comparison of Advanced Melting Process for HLW Vitrification, Joule-Heated Ceramic-Lined Melter (JHCM) and Cold-Crucible Induction Melter (CCIM)
Akira Sakai, Hajime Koikegami, Siegfried Weisenburger, Guenther Roth, Norio Kanehira, Satoshi Komamine
ICONE 2017; V007T10A038https://doi.org/10.1115/ICONE25-67807
Topics:
Ceramics
,
Electromagnetic induction
,
Joules
,
Melting
,
Vitrification
,
Glass
,
Metals
,
Spent nuclear fuels
,
Water
,
Borosilicate glasses
Application of Monte Carlo to PWR Cavity Radiation Streaming Calculation
ICONE 2017; V007T10A039https://doi.org/10.1115/ICONE25-67831
Topics:
Cavities
,
Pressurized water reactors
,
Radiation (Physics)
,
Monte Carlo methods
,
Simulation
,
Geometry
,
Accuracy and precision
,
Errors
,
Leakage
,
Neutron beams
Study of the Impact of Stellite Material on PWR Co-60 Contamination
ICONE 2017; V007T10A041https://doi.org/10.1115/ICONE25-67859
Topics:
Contamination
,
Pressurized water reactors
,
Cobalt
,
Corrosion
,
Radiation (Physics)
,
Design
,
Alloys
,
Circuits
,
Coolants
,
Flow (Dynamics)
The Removal of Uranium From Simulated Ammonium Diuranate Filtrate by Nanofiltration
ICONE 2017; V007T10A042https://doi.org/10.1115/ICONE25-67899
Topics:
Uranium
,
Membranes
,
Pressure
,
Permeability
,
Temperature
,
Testing
Study on Adsorption of U(VI) From Aqueous Solution by Activated MgO
ICONE 2017; V007T10A044https://doi.org/10.1115/ICONE25-67922
Topics:
Equilibrium (Physics)
,
Microwaves
,
Temperature
A Heat Dissipation Simulation Study in a CFD Way on Spent Nuclear Fuel Dry Stored in Underground Vertical Shaft
ICONE 2017; V007T10A045https://doi.org/10.1115/ICONE25-67926
Topics:
Computational fluid dynamics
,
Energy dissipation
,
Heat
,
Simulation
,
Spent nuclear fuels
,
Storage
,
Forced convection
,
Reliability
,
Safety
,
Security
Development and Application of the Device for Cutting and Disintegration of Radioactive Contamination Glove Box
ICONE 2017; V007T10A046https://doi.org/10.1115/ICONE25-67960
Topics:
Contamination
,
Cutting
,
Aerosols
,
Design
,
Gases
,
Nuclear decommissioning
,
Nuclear power stations
,
Stainless steel
US Department of Energy’s CoDCon Project: An Aqueous Safeguards R&D Program
ICONE 2017; V007T10A047https://doi.org/10.1115/ICONE25-67965
Topics:
Control systems
,
Decontamination
,
Design
,
Dynamic models
,
Industrial research
,
Instrumentation
,
Nuclear fuels
,
Nuclear power
,
Pacific Ocean
,
Plant design
Lessons Learned From the Operation of Large-Scale Reprocessing-Recycling Facilities in France: What Is in It for China?
ICONE 2017; V007T10A050https://doi.org/10.1115/ICONE25-68004
Topics:
China
,
Recycling
,
Spent nuclear fuels
,
Transparency
,
Governments
,
Negotiation
,
Nuclear fuel cycle
,
Nuclear power
,
Nuclear power stations
,
Safety
Mitigation Strategies for Beyond Design Basis Events
Study on Technical Scheme and Frame of Extreme Hazards Mitigation Guideline for CPR1000 NPP
ICONE 2017; V007T11A004https://doi.org/10.1115/ICONE25-66199
Topics:
Hazard mitigation
,
Nuclear power stations
,
Accidents
,
Containment
,
Damage
,
Floods
,
China
,
Control rooms
,
Damage assessment
,
Earthquakes
Studies on the Mitigation Strategies for Combustible Gases in a NPP
ICONE 2017; V007T11A005https://doi.org/10.1115/ICONE25-66326
Topics:
Gases
,
Nuclear power stations
,
Containment
,
Heat
,
Hydrogen
,
Control systems
,
Accidents
,
Vapors
A Method for Online Calibration of MAAP Simulations in a Severe Accident Management System Database
ICONE 2017; V007T11A006https://doi.org/10.1115/ICONE25-66431
Topics:
Accident management
,
Calibration
,
Databases
,
Simulation
,
Accidents
,
Failure
,
Uncertainty
,
Containment
,
Emergencies
,
Nuclear reactor accidents
An Integrated EDMG to Deal With Extensive Damage for NPPs in China
ICONE 2017; V007T11A008https://doi.org/10.1115/ICONE25-66451
Topics:
China
,
Damage
,
Nuclear power stations
,
Accident management
,
Accidents
,
Control rooms
,
Explosions
,
Fire
,
Control panels
,
Defense industry
Innovative Practice of Severe Accidents Measures in CAP1400
ICONE 2017; V007T11A009https://doi.org/10.1115/ICONE25-66605
Topics:
Accidents
,
Hydrogen
,
Containment
,
Design
,
Accident management
,
Feedback
,
Fukushima nuclear disaster, Japan, 2011
,
Risk
,
Safety
,
Combustion
On Different Break Section of LOCA Cases
ICONE 2017; V007T11A010https://doi.org/10.1115/ICONE25-66773
Topics:
Accidents
,
Nuclear power stations
,
Pressurized water reactors
,
Water
Research on IVR-Relevant Phenomena of Material Thermodynamic Interaction and Corium Pool Configuration
ICONE 2017; V007T11A011https://doi.org/10.1115/ICONE25-66969
Topics:
Accident management
,
Accidents
,
Cladding systems (Building)
,
Critical heat flux
,
Density
,
Design
,
Heart failure
,
Heat flux
,
Heat transfer
,
High temperature
The Study of CAP1400 Core Melt and Relocation for IVR Analysis
ICONE 2017; V007T11A012https://doi.org/10.1115/ICONE25-67008
Topics:
Accidents
,
Computational fluid dynamics
,
Corners (Structural elements)
,
Failure
,
Finite element analysis
,
Fuels
,
Heat
,
Heat flux
,
Melting
,
Metals
Analysis on Hydrogen Risk Induced by Containment Leakage
ICONE 2017; V007T11A013https://doi.org/10.1115/ICONE25-67012
Topics:
Containment
,
Hydrogen
,
Leakage
,
Risk
,
Accidents
,
Annulus
,
Condensation
,
Explosions
,
Failure
,
Fukushima nuclear disaster, Japan, 2011
VINSAP Tool for Visualization of Severe Accident Progress
ICONE 2017; V007T11A016https://doi.org/10.1115/ICONE25-67123
Topics:
Accidents
,
Visualization
,
Nuclear power stations
,
Computer software
,
Testing
In-Vessel Corium Behavior and Steam Explosion Risks: A Review of Experimental Approaches
ICONE 2017; V007T11A017https://doi.org/10.1115/ICONE25-67176
Topics:
Experimental methods
,
Explosions
,
Steam
,
Vessels
,
Coolants
,
Heat transfer
,
Reactor vessels
,
Accident management
,
Accidents
,
Containment
Study on the Application of CDAG Methodology in EPR Nuclear Power Plant
ICONE 2017; V007T11A018https://doi.org/10.1115/ICONE25-67248
Topics:
Nuclear power stations
,
Damage assessment
,
Damage
,
Accidents
,
Design
,
Nuclear fission
,
Containment
,
Emergency response
,
Fuels
,
Nuclear power
Long-Term Cooling Strategy for the Primary Containment Vessel of the Kashiwazaki-Kariwa Nuclear Power Station in a Severe Accident
ICONE 2017; V007T11A019https://doi.org/10.1115/ICONE25-67317
Topics:
Accidents
,
Containment vessels
,
Cooling
,
Nuclear power stations
,
Heat
,
Temperature
,
Heat exchangers
,
Water
,
Pumps
,
Reliability
Fluid Dynamic Analysis on Hydrogen Deflagration in Vertical Flow Channel With Annular Obstacles
ICONE 2017; V007T11A020https://doi.org/10.1115/ICONE25-67520
Topics:
Dynamic analysis
,
Explosions
,
Flow (Dynamics)
,
Fluids
,
Hydrogen
,
Flames
,
Combustion
,
Accidents
,
Chemical reactions
,
Computational fluid dynamics
Scaling Analysis of Scrubber Pool and Cyclone for Filtered Containment Venting System Testing
ICONE 2017; V007T11A021https://doi.org/10.1115/ICONE25-67598
Topics:
Containment
,
Testing
,
Filters
,
Engineering prototypes
,
Flow (Dynamics)
,
Nozzles
,
Pressure
,
Accidents
,
Design
,
Particulate matter
Accessibility Analysis for Staff After Accident of PWR Unit
ICONE 2017; V007T11A022https://doi.org/10.1115/ICONE25-67678
Study on Hydrogen Risk of Spent Fuel Compartment Induced by Containment Venting
ICONE 2017; V007T11A023https://doi.org/10.1115/ICONE25-67800
Topics:
Containment
,
Hydrogen
,
Risk
,
Spent nuclear fuels
,
Control systems
,
Accident management
,
Accidents
,
Cooling
,
Fukushima nuclear disaster, Japan, 2011
,
Heat
Source Term Analysis Considering B4C/Steel Interaction and Oxidation During Severe Accidents
ICONE 2017; V007T11A024https://doi.org/10.1115/ICONE25-67858
Topics:
Accidents
,
Oxidation
,
Steel
,
Boiling water reactors
,
Carbon dioxide
,
Water
,
Boron
,
Chemistry
,
Containment vessels
,
Coolants
Preliminary Study on the Identification of DECs Without Significant Fuel Degradation in New NPP Designs
ICONE 2017; V007T11A026https://doi.org/10.1115/ICONE25-68012
Topics:
Fuels
,
Nuclear power stations
,
Safety
,
Accidents
,
Design
,
China
,
Nuclear power
,
Fukushima nuclear disaster, Japan, 2011
,
Melting