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Proceedings Papers
Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues
Smart Grids, Grid Stability, and Offsite and Emergency Power
Results of the Loss of Offsite Power Events Analysis
ICONE 2016; V002T05A001https://doi.org/10.1115/ICONE24-60153
Topics:
Control rooms
,
Databases
,
Diesel generators
,
Emergencies
,
Errors
,
Failure
,
Inspection
,
Maintenance
,
Power grids
Trend Analysis of Loss of Offsite Power Events
ICONE 2016; V002T05A002https://doi.org/10.1115/ICONE24-60154
Topics:
Trend analysis
,
Databases
,
Statistical analysis
Degraded Power Supplies
ICONE 2016; V002T05A003https://doi.org/10.1115/ICONE24-60255
Topics:
Countermeasures
,
Design
,
Electricity (Physics)
,
Nuclear power stations
,
Radiation (Physics)
,
Reliability
,
Robustness
,
Safety
Coordinated Control Strategy of Multiple FACTS Devices in 750kV Power Grid
ICONE 2016; V002T05A005https://doi.org/10.1115/ICONE24-60519
Topics:
Power grids
,
Wind power
,
Transients (Dynamics)
Study on Power Transmission Plan of the Nuclear Power Base in Shandong Peninsula
ICONE 2016; V002T05A007https://doi.org/10.1115/ICONE24-60645
Topics:
Nuclear power
,
Power grids
,
Construction
,
Stress
,
Circuits
,
Nuclear power stations
,
Electrical wires
,
Generators
,
Poles (Building)
,
Power stations
Long Term Operation Issues for Electrical Cable Systems in Nuclear Power Plants
ICONE 2016; V002T05A008https://doi.org/10.1115/ICONE24-60729
Topics:
Cables
,
Nuclear power stations
,
Insulation
,
Damage
,
Design
,
Heat
,
Licensing
,
Polymers
,
Radiation (Physics)
,
Temperature
Dynamic Simulation Studies of Performed Additional Tests During FAT for Emergency Diesel Generators at Nuclear Power Plant
ICONE 2016; V002T05A012https://doi.org/10.1115/ICONE24-61084
Topics:
Diesel generators
,
Emergencies
,
Nuclear power stations
,
Simulation
,
Control equipment
,
Magnetization
,
Modeling
,
Safety
,
Circuits
,
Diesel engines
Advanced and Next Generation Reactors, Fusion Technology
Simulation Study of Dynamic Characteristic of Once-Through Steam Generator for CEFR
ICONE 2016; V002T06A001https://doi.org/10.1115/ICONE24-60017
Topics:
Boilers
,
Simulation
,
Steam
,
China
,
Convection
,
Critical heat flux
,
Fast neutron reactors
,
Film boiling
,
Flow (Dynamics)
,
Heart failure
Analysis of the Effects Caused by the Core Compaction Into LFR Reactor
ICONE 2016; V002T06A002https://doi.org/10.1115/ICONE24-60022
Topics:
Compacting
,
Buckling
,
Coolants
,
Deformation
,
Displacement
,
Earthquakes
,
Fast neutron reactors
,
Finite element methods
,
Finite element model
,
Fuels
Experimental Study of Steam Pressure Suppression by Condensation in a Water Tank at Sub-Atmospheric Pressure
ICONE 2016; V002T06A003https://doi.org/10.1115/ICONE24-60029
Topics:
Condensation
,
Pressure
,
Steam
,
Water
,
Accidents
,
Vacuum
,
Temperature
,
Vessels
,
Atmospheric pressure
,
Boiling
Development of the Pump-Integrated Intermediate Heat Exchanger in Advanced Loop-Type Sodium-Cooled Fast Reactor for Demonstration
ICONE 2016; V002T06A004https://doi.org/10.1115/ICONE24-60064
Topics:
Heat exchangers
,
Pumps
,
Sodium fast reactors
,
Design
,
Safety
,
Coolants
,
Earthquakes
,
Leakage
,
Maintainability
,
Nuclear power
Research on Manufacturing Technology of China Experimental Fast Reactor Fuel Rod
ICONE 2016; V002T06A005https://doi.org/10.1115/ICONE24-60076
Topics:
China
,
Fast neutron reactors
,
Fuel rods
,
Manufacturing technology
,
Manufacturing
,
Welding
,
Wire
,
Cladding systems (Building)
,
Extruding
,
Fuels
Study on the Break Accidents of the HTR-PM Primary Loop
ICONE 2016; V002T06A006https://doi.org/10.1115/ICONE24-60113
Topics:
Accidents
,
Helium
,
Containment
,
Coolants
,
Pressure
,
Temperature
,
Boilers
,
Design
,
High temperature
,
Leakage
Transient Analysis on Helium Coolant Tube Break Accident of Dual-Functional Lithium Lead Test Blanket Module
ICONE 2016; V002T06A007https://doi.org/10.1115/ICONE24-60123
Topics:
Accidents
,
Coolants
,
Helium
,
Lithium
,
Transient analysis
,
Pressure
,
Shock (Mechanics)
,
China
,
Corners (Structural elements)
,
Flow (Dynamics)
Thermo-Hydraulic Analysis of the Optimized Helium Cooled Solid Breeder Blanket for CFETR
ICONE 2016; V002T06A008https://doi.org/10.1115/ICONE24-60144
Topics:
Helium
,
Temperature
,
Design
,
Temperature distribution
,
Ceramics
,
China
,
Computational fluid dynamics
,
Coolants
,
Cooling
,
Dynamic analysis
A Study on the Straight Double-Walled Tube Steam Generator Design Against Sodium-Water Reaction in DECs
Hironori Kanda, Yasuhiro Enuma, Satoshi Futagami, Masaya Kawamura, Hiroshi Ushiki, Shinya Ogumo, Takashi Ichihara, Takashi Nakashima
ICONE 2016; V002T06A009https://doi.org/10.1115/ICONE24-60156
Topics:
Boilers
,
Design
,
Sodium
,
Water
,
Failure
,
Sodium fast reactors
,
Water leakage
,
Contact resistance
,
Temperature
,
Leakage
Design Approach for Mitigation of Air Ingress in High Temperature Gas-Cooled Reactor
ICONE 2016; V002T06A010https://doi.org/10.1115/ICONE24-60232
Topics:
Design
,
Very high temperature reactors
,
Oxidation
,
Accidents
,
Fuels
,
Rupture
,
Buoyancy
,
Cooling
,
Damage
,
Flow (Dynamics)
Accurate Simulation of HTGR Steam Generator for Pressurized Loss of Forced Cooling Accident
ICONE 2016; V002T06A012https://doi.org/10.1115/ICONE24-60333
Topics:
Accidents
,
Boilers
,
Cooling
,
Simulation
,
Very high temperature reactors
,
Circuits
,
Heat capacity
,
Algorithms
,
Approximation
,
Boundary-value problems
Kinetic Monte Carlo Simulation of Hydrogen Diffusion in Tungsten
ICONE 2016; V002T06A013https://doi.org/10.1115/ICONE24-60352
Topics:
Diffusion (Physics)
,
Hydrogen
,
Simulation
,
Tungsten
,
Temperature
,
Modeling
,
Matlab
,
Simulation models
,
Simulation results
Characteristic Confirmation Test by Using HTTR and Investigation of Absorbing Thermal Load Fluctuation
Yuki Honda, Daisuke Tochio, Hiroyuki Sato, Shigeaki Nakagawa, Masato Ono, Yusuke Fujiwara, Shimpei Hamamoto, Kazuhiko Iigaki, Shoji Takada
ICONE 2016; V002T06A014https://doi.org/10.1115/ICONE24-60355
Nuclear, Solar and Desalination Working Together Symbiotically
ICONE 2016; V002T06A015https://doi.org/10.1115/ICONE24-60362
Topics:
Solar energy
,
Fossil fuels
,
Combustion
,
Emissions
,
Energy / power systems
,
Fuels
,
Gases
,
Nuclear power
,
Solar power
,
Transportation systems
Neutronics and Thermo-Hydraulic Analysis of Water-Cooled Blanket Based on PWR and SCWR Water Conditions for CFETR
ICONE 2016; V002T06A017https://doi.org/10.1115/ICONE24-60392
Topics:
Pressurized water reactors
,
Supercritical water reactors
,
Water
,
China
,
Heat
,
Temperature
,
Bridges (Structures)
,
Ceramics
,
Computer simulation
,
Coolants
Analyses of Severe Accidents in GFR Demonstrator ALLEGRO With MELCOR 2.1
ICONE 2016; V002T06A018https://doi.org/10.1115/ICONE24-60396
Topics:
Accidents
,
Fast neutron reactors
,
Safety
,
Cladding systems (Building)
,
Computer simulation
,
Computers
,
Coolants
,
Damage
,
Design
,
Failure
Investigation of the Modified RELAP5 MOD 3.2 Capability to Simulate the Transients of the Fluoride-Salt High-Temperature Reactors
ICONE 2016; V002T06A019https://doi.org/10.1115/ICONE24-60429
Topics:
High temperature
,
Transients (Dynamics)
,
Accidents
,
Flow (Dynamics)
,
Fluids
,
Fuels
,
Heat
,
Specific heat
,
Steady state
Comparative Study on Neutronics Characteristics of a 1500 MWe Metal Fuel Sodium-Cooled Fast Reactor
ICONE 2016; V002T06A020https://doi.org/10.1115/ICONE24-60455
Topics:
Fuels
,
Metals
,
Sodium fast reactors
,
Nuclear power
,
Approximation
,
Cycles
,
Design
,
Neutrons
,
Sensitivity analysis
,
Sodium
Activities of the Safety and Operation Project for the International Research and Development of the Sodium-Cooled Fast Reactor in the Generation IV International Forum
Takaaki Sakai, Lixia Ren, Haileyesus Tsige-Tamirat, Alfredo Vasile, Seok-Hun Kang, Yury Ashurko, Thomas Fanning
ICONE 2016; V002T06A021https://doi.org/10.1115/ICONE24-60502
Topics:
Industrial research
,
Safety
,
Sodium fast reactors
,
Testing
,
Design
,
Generation IV reactors
,
Licensing
,
Maintenance
,
Model validation
,
Nuclear power
Confirmation of Seismic Integrity of HTTR Against 2011 Great East Japan Earthquake
Masato Ono, Kazuhiko Iigaki, Yosuke Shimazaki, Atsushi Shimizu, Hiroyuki Inoi, Daisuke Tochio, Shimpei Hamamoto, Tetsuo Nishihara, Shoji Takada, Kazuhiro Sawa, Toshinari Kondo, Keidai Kojima
ICONE 2016; V002T06A023https://doi.org/10.1115/ICONE24-60571
Impact of Testing Activities on Small Modular Reactor Total Capital Investment Cost
ICONE 2016; V002T06A024https://doi.org/10.1115/ICONE24-60675
Topics:
Small modular reactors
,
Testing
,
Manufacturing
,
Construction
,
Design
,
Nuclear power stations
,
Computer software
,
Modular construction
,
Teams
,
Uncertainty
Assessment of SIMMER-III Code Based on Steam Generator Tube Rupture Experiments in LIFUS5/Mod2 Facility
ICONE 2016; V002T06A025https://doi.org/10.1115/ICONE24-60711
Topics:
Boilers
,
Rupture
,
Water
,
Pressure
,
Underground injection
,
Vessels
,
Boundary-value problems
,
Computer simulation
,
Computers
,
Cooling
Experimental Investigation of Spiral Tubes Steam Generator Rupture Scenarios in LIFUS5/Mod2 Facility for ELFR
ICONE 2016; V002T06A026https://doi.org/10.1115/ICONE24-60715
Topics:
Boilers
,
Rupture
,
Pressure
,
Water
,
Strain gages
,
Vessels
,
Deformation
,
Ejectors
,
Eutectic alloys
,
Fast neutron reactors
Test Section Design for SGTR Experimental Investigation in CIRCE Facility for HLMRS Supported by SIMMER-III Code
ICONE 2016; V002T06A027https://doi.org/10.1115/ICONE24-60716
Topics:
Design
,
Rupture
,
Disks
,
Vessels
,
Boilers
,
Heat exchangers
,
Pressure
,
Transients (Dynamics)
,
Underground injection
,
Water
RELAP5-3D Simulation of Natural Circulation in Fast Reactors With Lead-Bismuth Eutectic Alloy Coolant
ICONE 2016; V002T06A028https://doi.org/10.1115/ICONE24-60734
Topics:
Coolants
,
Eutectic alloys
,
Fast neutron reactors
,
Simulation
,
Nuclear reactors
,
Design
,
Fuels
,
Nuclear fission
,
Safety
,
Simulation results
A Methodology for the Integration of Passive System Reliability With Success Criteria in a Probabilistic Framework for Advanced Reactors
ICONE 2016; V002T06A029https://doi.org/10.1115/ICONE24-60749
Topics:
Reliability
,
Safety
,
Feedback
,
Industrial research
,
Light water reactors
,
Nuclear power
,
Performance
,
Prisms (Optics)
,
Probabilistic risk assessment
,
Risk
A Methodology for the Integration of a Mechanistic Source Term Analysis in a Probabilistic Framework for Advanced Reactors
ICONE 2016; V002T06A030https://doi.org/10.1115/ICONE24-60759
Topics:
Containment
,
Fuels
,
Industrial research
,
Light water reactors
,
Nuclear power
,
Performance
,
Probabilistic risk assessment
,
Radioisotopes
,
Reliability
,
Risk
Start-Up Simulation of the Improved TOPAZ-II Space Power System
ICONE 2016; V002T06A032https://doi.org/10.1115/ICONE24-60829
Topics:
Power systems (Machinery)
,
Simulation
,
Heat pipes
,
Coolants
,
Ducts
,
Neutrons
,
Physics
,
Pipes
,
Pumps
,
Secondary cells
Improvement of Exchanging Method of Neutron Startup Source of High Temperature Engineering Test Reactor
Hiroaki Sawahata, Yosuke Shimazaki, Etsuo Ishitsuka, Kazunori Yamazaki, Yoshinori Yanagida, Yusuke Fujiwara, Shoji Takada, Masayuki Shinozaki, Shimpei Hamamoto, Daisuke Tochio
ICONE 2016; V002T06A033https://doi.org/10.1115/ICONE24-60842
Topics:
High temperature
,
Neutrons
,
Containers
,
Fuels
,
Leakage
,
Machinery
,
Neutron sources
,
Radiation (Physics)
,
Transportation systems
,
Cooling
Thermal Mixing Behavior in the Annulus of Co-Axial Double-Walled Piping in HTGR
Daisuke Tochio, Yusuke Fujiwara, Masato Ono, Masanori Shinohara, Shimpei Hamamoto, Kazuhiko Iigaki, Shoji Takada
ICONE 2016; V002T06A034https://doi.org/10.1115/ICONE24-60843
Topics:
Annulus
,
Pipes
,
Very high temperature reactors
,
Helium
,
Temperature
,
Flow (Dynamics)
,
Coolants
,
Cooling systems
,
Gas flow
,
Gases
Loss of Core Cooling Test Without One Cooling Line in Vessel Cooling System (VCS) of High Temperature Engineering Test Reactor (HTTR)
Yusuke Fujiwara, Takahiro Nemoto, Daisuke Tochio, Masanori Shinohara, Masato Ono, Shimpei Hamamoto, Kazuhiko Iigaki, Shoji Takada
ICONE 2016; V002T06A035https://doi.org/10.1115/ICONE24-60858
Topics:
Cooling
,
Cooling systems
,
High temperature
,
Vessels
,
Temperature
,
Reactor vessels
,
Concretes
,
Heat
,
Helium
,
Control systems
Preliminary Analysis of the Post-Disassembly Expansion Phase and Structural Response Under Unprotected Loss of Flow Accident in Prototype Sodium Cooled Fast Reactor
ICONE 2016; V002T06A037https://doi.org/10.1115/ICONE24-60893
Topics:
Accidents
,
Engineering prototypes
,
Flow (Dynamics)
,
Sodium fast reactors
,
Energetics
,
Reactor vessels
,
Energy generation
,
Robustness
,
Stress
,
Design
iB1350: Innovative Passive Containment Cooling System for the iB1350
ICONE 2016; V002T06A039https://doi.org/10.1115/ICONE24-60919
Topics:
Containment
,
Cooling systems
,
Pipes
,
Suction
,
Gases
,
Steam
,
Pressure
,
Vents
,
Accidents
,
Boiling
Safety, Security, and Cyber Security
Preliminary Study of Function Determination and Capacity of ACP600’s Reactor Emergency Borating System
ICONE 2016; V002T07A001https://doi.org/10.1115/ICONE24-60024
Topics:
Emergencies
,
Design
,
Safety
,
Nuclear power stations
,
Accidents
,
Boron
,
China
,
Concretes
,
Feedback
,
Pressurized water reactors
Research on Thermal Hydraulic Characteristics of Passive Containment Cooling System for Ship Nuclear Power Platform
ICONE 2016; V002T07A003https://doi.org/10.1115/ICONE24-60173
Topics:
Containment
,
Cooling systems
,
Nuclear power
,
Ships
,
Steam
,
Heat
,
Seawater
,
Heat transfer
,
Pressure
,
Accidents
Preparation for a New Experimental Program Addressing Core-Material-Relocation Behavior During Severe Accident With BWR Design Conditions: Conduction of Preparatory Tests Applying Non-Transfer-Type Plasma Heating Technology
ICONE 2016; V002T07A004https://doi.org/10.1115/ICONE24-60249
Topics:
Accidents
,
Boiling water reactors
,
Design
,
Heat conduction
,
Heating
,
Plasmas (Ionized gases)
,
Blades
,
Rods
,
Uncertainty
Development of Transient and Safety Analysis Method for ATF With SiC
ICONE 2016; V002T07A005https://doi.org/10.1115/ICONE24-60250
Topics:
Safety
,
Transients (Dynamics)
,
Accidents
,
Oxidation
,
Water
,
Transient analysis
,
Cladding systems (Building)
,
Fuels
,
High temperature
,
Hydrogen
Safety Assessment of Fuel Storage Ponds Following Cooling Faults
ICONE 2016; V002T07A006https://doi.org/10.1115/ICONE24-60267
Topics:
Cooling
,
Fuel storage
,
Safety
,
Water
,
Temperature
,
Containment
,
Cooling systems
,
Spent nuclear fuels
,
Concretes
,
Cracking (Materials)
Review of Experimental Studies on the Heat Transfer Behaviour of Volumetrically-Heated Pool With Different Boundary Conditions and the Influence of Crust Formation
ICONE 2016; V002T07A007https://doi.org/10.1115/ICONE24-60268
Topics:
Boundary-value problems
,
Heat transfer
,
Accident management
,
Cooling
,
Geometry
,
Heat flux
,
Light water reactors
,
Vessels
Development of Error Reduction Methods in Aerosol Measurement for Pool Scrubbing Experiment
ICONE 2016; V002T07A008https://doi.org/10.1115/ICONE24-60359
Topics:
Aerosols
,
Errors
,
Air flow
,
Particulate matter
,
Water
,
Bubbles
,
Accidents
,
Decontamination
,
Filters
,
Light scattering
Analysis on Safety System Operating Characteristic of SCWR
ICONE 2016; V002T07A009https://doi.org/10.1115/ICONE24-60501
Topics:
Safety
,
Supercritical water reactors
,
Control systems
,
Accidents
,
Flow (Dynamics)
,
Oscillations
,
Passive control
,
Pressure control
,
Water
Development of Hydrogen Treatment System in Severe Accident: Part 2 — Study on Reaction Characteristic of a Hydrogen Processing Unit
Chikako Iwaki, Daigo Kittaka, Toshihiro Yoshii, Motoshige Yagyu, Masato Okamura, Masashi Tanabe, Fumihiko Ishibashi
ICONE 2016; V002T07A012https://doi.org/10.1115/ICONE24-60917
Topics:
Accidents
,
Hydrogen
,
Metals
,
Pipes
,
Pressure
,
Temperature
,
Vents
,
Boiling water reactors
,
Filters
,
Oxidation
Methodology for Fragility Evaluation of a Seawall Against Tsunami Effects: Part 1 — Overflow and Physical Damage Associated With Tsunami Wave Pressure
ICONE 2016; V002T07A013https://doi.org/10.1115/ICONE24-60927
Topics:
Damage
,
Pressure
,
Seawalls
,
Tsunamis
,
Waves
,
Nuclear power stations
,
Accidents
,
Compressive strength
,
Concretes
,
Density
Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues
Suggested Guide for Geotechnical Sampling and Testing of Backfill and Borrow for Safety Related Nuclear Structures
ICONE 2016; V002T08A001https://doi.org/10.1115/ICONE24-60004
Topics:
Construction
,
Cycles
,
Delays
,
Design
,
Licensing
,
Nuclear industry
,
Nuclear power stations
,
Quality control
,
Regulations
,
Roads
Strategies to Prevent Benign Transients From Becoming Serious Accidents
ICONE 2016; V002T08A004https://doi.org/10.1115/ICONE24-60472
Topics:
Accidents
,
Plant design
,
Safety
,
Transients (Dynamics)
Regulatory Actions That Hinder Development of Effective Risk Reduction Measures by the Nuclear Industry for Enhanced Severe Accident Prevention and Mitigation Measures After Fukushima
ICONE 2016; V002T08A005https://doi.org/10.1115/ICONE24-60700
Topics:
Fukushima nuclear disaster, Japan, 2011
,
Nuclear industry
,
Risk reduction
,
Safety
,
Accidents
,
Public utilities
,
Risk
,
Silence
,
Damage
,
Emergencies
Development of Rules on Concrete Containment Vessels for NPP
Tomohiro Nishizawa, Takao Nishikawa, Katsuki Takiguchi, Hiroyuki Sugita, Yasuo Hijioka, Hirokazu Tsuji
ICONE 2016; V002T08A008https://doi.org/10.1115/ICONE24-60958
Topics:
Concretes
,
Containment vessels
,
Nuclear power stations
,
Construction
,
Design
,
Prestressed concrete
,
Reinforced concrete
,
Reliability
,
Safety
,
Steel
Outline of Specification for Composite SC Walls in Nuclear Facilities
ICONE 2016; V002T08A009https://doi.org/10.1115/ICONE24-60960
Topics:
Composite materials
,
Nuclear power stations
,
Design
,
Shear (Mechanics)
,
Steel
,
Failure
,
Safety
,
Accidents
,
Anchorage
,
Bending (Stress)
Implementation of Reliability Evaluation Into JSME Fast Reactor Codes: 2 — Development of a Code Case for Seismic Buckling Evaluation Based on LRFD
ICONE 2016; V002T08A010https://doi.org/10.1115/ICONE24-60964
Topics:
Buckling
,
Fast neutron reactors
,
Japan Society of Mechanical Engineers
,
Reliability
,
Design
,
Stress
,
Probability
,
Vessels
,
Civil engineering
,
Earthquake risk
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