Skip Nav Destination
Proceedings Papers
Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application
Nuclear Fuel and Material, Reactor Physics and Transport Theory
Multi-Dimensional Shield Performance Analysis Through an Even Parity Based “Contributon” Transport Concept
ICONE 2017; V003T02A005https://doi.org/10.1115/ICONE25-66124
Topics:
Parity (Physics)
,
Flux (Metallurgy)
,
Finite element methods
,
Design
,
Neutrons
,
Polynomials
,
Robustness
,
Sensors
,
Variational principles
Analysis of Fast Reactor Fuel Irradiation Behavior in the MA Recycle System
ICONE 2017; V003T02A006https://doi.org/10.1115/ICONE25-66129
Topics:
Fast neutron reactors
,
Fuels
,
Irradiation (Radiation exposure)
,
Cladding systems (Building)
,
Temperature
,
Corrosion
,
Hazards
,
Heavy metals
,
Helium
,
Melting
Performances Analyses of Crud of EPR Fuel Assembly
ICONE 2017; V003T02A007https://doi.org/10.1115/ICONE25-66204
Research on Detailed Depletion Chain Solving Algorithm With the NUIT Code
ICONE 2017; V003T02A008https://doi.org/10.1115/ICONE25-66238
Topics:
Algorithms
,
Chain
,
Nuclides
,
Approximation
,
Polynomial approximation
A New Numerical Method for Fuel Temperature Calculation
ICONE 2017; V003T02A009https://doi.org/10.1115/ICONE25-66248
Topics:
Fuels
,
Numerical analysis
,
Temperature
,
Heat conduction
,
Stability
,
Fuel rods
,
Thermal conductivity
,
Density
,
Dimensions
,
Specific heat
Simulation on Neutron Space-Time Kinetics for Accelerator Driven Sub-Critical System
ICONE 2017; V003T02A010https://doi.org/10.1115/ICONE25-66314
Topics:
Neutrons
,
Simulation
,
Spacetime
,
Neutron flux
,
Temperature
,
Transients (Dynamics)
,
Approximation
,
Coolants
,
Fuels
,
Physics
Application of a 3D Discrete Ordinates-Monte Carlo Coupling Method on CAP1400 Cavity Streaming Calculation
ICONE 2017; V003T02A011https://doi.org/10.1115/ICONE25-66401
Topics:
Cavities
,
Fluence (Radiation measurement)
,
Neutrons
,
Photons
,
Errors
,
Computation
,
Dimensions
,
Geometry
,
Modeling
,
Nuclear power stations
Burnable Poisons Alternative Configurations in AT-FCM PWR Fuel Assembly
ICONE 2017; V003T02A012https://doi.org/10.1115/ICONE25-66444
Topics:
Fuels
,
Manufacturing
,
Pressurized water reactors
,
Boron
,
Cycles
,
Nuclear reactors
,
Safety
,
Accidents
,
High temperature
,
Ceramics
Newly Developed Coupling Scheme in RMC With Internal Thermal Feedback and OTF Doppler-Broadening Method
ICONE 2017; V003T02A014https://doi.org/10.1115/ICONE25-66519
Topics:
Feedback
,
Nuclear reactors
,
Steady state
,
Fuels
,
Hydraulics
,
Manufacturing
,
Physics
,
Pressurized water reactors
,
Simulation
,
Simulation analysis
New Exploration on TMSR: Redesign of the TMSR Lattice
ICONE 2017; V003T02A016https://doi.org/10.1115/ICONE25-66564
Topics:
Breeder reactors
,
Ceramics
,
Cladding systems (Building)
,
Coolants
,
Corrosion
,
Design
,
Fast neutron reactors
,
Flow (Dynamics)
,
Fluids
,
Fuels
Development and Verification of the PWR Lattice Code PANDA
ICONE 2017; V003T02A018https://doi.org/10.1115/ICONE25-66573
Topics:
Pressurized water reactors
,
Collapse
,
Cross section (Physics)
,
Design
,
Nuclear design
,
Nuclear engineering
,
Physics
,
Resonance
Out-of-Pile Properties Investigation of UO2-BeO Fuel Pellet
ICONE 2017; V003T02A019https://doi.org/10.1115/ICONE25-66585
Topics:
Fuels
,
Thermal conductivity
,
Elastic moduli
,
Thermal expansion
,
Uranium
,
Composite materials
,
Nuclear power stations
,
Sintering
Test Reactor Irradiation Fuel Assembly Development in China
ICONE 2017; V003T02A020https://doi.org/10.1115/ICONE25-66617
Topics:
China
,
Fuels
,
Irradiation (Radiation exposure)
,
Manufacturing
,
Zirconium alloys
,
Alloys
,
Corrosion
,
Creep
,
Finishes
,
Fuel rods
An Innovative Spherical Fuel Element to Inhibit the Infiltration of Liquid Fluoride Salt in Molten Salt Reactor
ICONE 2017; V003T02A023https://doi.org/10.1115/ICONE25-66639
Topics:
Fuels
,
Molten salt reactors
,
Graphite
,
Shells
,
Density
,
Stress
,
Design
,
Operating temperature
,
Porosity
,
Safety
Research and Engineering Application of Repaired Fuel Assembly Reusing Technique
Lihua Wang, Qingxiang Yang, Ping Yang, Jiazheng Liu, Libing Zhu, Bo Yang, Hong Cao, Zhe Wang, Yang Ding, Jie Ding
ICONE 2017; V003T02A024https://doi.org/10.1115/ICONE25-66659
Topics:
Fuels
,
Manufacturing
,
Design
,
Fuel rods
,
Nuclear power stations
,
Economics
,
Rods
,
Safety
,
Computer software
,
Coolants
CAP1400 Fuel Assembly Development and PWR Fuel Assembly Technology Progress in China
Libing Zhu, Jie Ding, Qin Zhou, Yunqing Zhou, Fujun Gan, Junqiang Lu, Yixiong Zheng, Jiwei Li, Yang Ding, Qifeng Zeng, Song Liu
ICONE 2017; V003T02A025https://doi.org/10.1115/ICONE25-66700
Topics:
China
,
Fuels
,
Manufacturing
,
Pressurized water reactors
,
Irradiation (Radiation exposure)
,
Alloys
,
Cladding systems (Building)
,
Design
,
Fuel rods
,
Reliability
Preparation and Properties Investigation of Neutron Absorber Material Mo-Tb-Dy and Y-Tb-Dy Alloys
ICONE 2017; V003T02A026https://doi.org/10.1115/ICONE25-66747
Topics:
Alloys
,
Neutrons
,
Irradiation (Radiation exposure)
,
Temperature
,
Corrosion
,
Atoms
,
Corrosion resistance
,
Density
,
Diluents
,
Displacement
Simulation on Pellet-Cladding Mechanical Interaction (PCMI) of Accident Tolerant Fuel (ATF) With Coated Cladding
ICONE 2017; V003T02A027https://doi.org/10.1115/ICONE25-66774
Topics:
Accidents
,
Cladding systems (Building)
,
Fuels
,
Simulation
,
Coatings
,
Zirconium
,
Alloys
,
Fuel rods
,
Pressure
,
Stress
Methodology to Construct Burnup Profile of Fuel Pebbles in PBR
ICONE 2017; V003T02A029https://doi.org/10.1115/ICONE25-66795
Topics:
Fuels
,
Discrete element methods
,
Flow (Dynamics)
,
Economics
,
Safety
,
Cycles
,
Gas cooled reactors
,
Irradiation (Radiation exposure)
,
Kinematics
,
Simulation
Crucial Factors Analysis of 5×5 Grid Flow-Induced Vibration Test
ICONE 2017; V003T02A031https://doi.org/10.1115/ICONE25-66812
Topics:
Flow-induced vibrations
,
Vibration
,
Manufacturing
,
Flow (Dynamics)
,
Fuels
,
Pressure
,
Water
,
Abrasion
,
Fuel rods
,
Laser Doppler vibrometers
Stress Analysis of Three-Layer SiC Cladding for PWRs
ICONE 2017; V003T02A032https://doi.org/10.1115/ICONE25-66814
Small Punch Test on Mechanical Properties of Molybdenum Single Crystal Weld
ICONE 2017; V003T02A033https://doi.org/10.1115/ICONE25-66824
Topics:
Crystals
,
Mechanical properties
,
Molybdenum
,
Displacement
,
Stress
,
Yield strength
,
Brittleness
,
Creep
,
Electron beam welding
,
Embrittlement
SCORPIO-VVER: Two Decades of Experience and Enhancements in Reactor Core Monitoring and Surveillance in Central Europe
ICONE 2017; V003T02A034https://doi.org/10.1115/ICONE25-66867
Topics:
Surveillance
,
Fuels
,
Construction
,
Monitoring systems
,
Nuclear power stations
,
Computation
,
Computers
,
Design
,
Education
,
Engineers
A Resolution Enhancing Algorithm for Gamma-Ray Spectrum Based on Blind Deconvolution and Lp-Norm Sparsity Constraint
ICONE 2017; V003T02A035https://doi.org/10.1115/ICONE25-66923
Topics:
Algorithms
,
Gamma rays
,
Resolution (Optics)
,
Emission spectroscopy
,
Oscillations
,
Spectroscopy
,
Computer simulation
The Verification of SONG Library
ICONE 2017; V003T02A036https://doi.org/10.1115/ICONE25-66946
Microstructure and Properties of New Zirconium Alloys for CAP1400 Fuel Assembly
ICONE 2017; V003T02A037https://doi.org/10.1115/ICONE25-66951
Topics:
Fuels
,
Manufacturing
,
Zirconium alloys
,
Alloys
,
Corrosion resistance
,
Creep
,
Mechanical properties
,
Design
,
Temperature
,
Water chemistry
Effects of Annealing on the Corrosion Property of CZ1 Alloy
ICONE 2017; V003T02A038https://doi.org/10.1115/ICONE25-67035
Topics:
Alloys
,
Annealing
,
Corrosion
,
Cladding systems (Building)
,
Corrosion resistance
,
Particulate matter
,
Zirconium
,
China
,
Design
,
Fuels
Annealing Temperature Effect on Creep Property of CZ Alloy for PWR Modern Fuel Claddings
Yang Xu, Jun Tan, Liu-tao Chen, Dun-gu Wen, Hong Zou, Chang-yuan Gao, Xu Wang, Si-si Dong, Wei-jun Wang
ICONE 2017; V003T02A039https://doi.org/10.1115/ICONE25-67054
Topics:
Alloys
,
Annealing
,
Creep
,
Fuels
,
Pressurized water reactors
,
Temperature
,
Zirconium alloys
,
Stress
,
China
,
Cladding systems (Building)
Modeling and Thermal Calculation of Fuel Rod With SiCf/SiC Cladding for LWRs
ICONE 2017; V003T02A040https://doi.org/10.1115/ICONE25-67078
Topics:
Cladding systems (Building)
,
Fuel rods
,
Light water reactors
,
Modeling
,
Fuels
,
Composite materials
,
Design
,
Fibers
,
Fluence (Radiation measurement)
,
Neutrons
Research on Nickel-Plated Hydrogen-Absorption Device in Fuel Rod and Performance Testing
ICONE 2017; V003T02A041https://doi.org/10.1115/ICONE25-67112
Topics:
Absorption
,
Fuel rods
,
Hydrogen
,
Nickel plating
,
Testing performance
,
Cladding systems (Building)
,
Design
,
Pressure
,
Zirconium
,
Alloys
Modeling of Fuel Rod Behavior and Recent Advances of the JASMINE Code
ICONE 2017; V003T02A043https://doi.org/10.1115/ICONE25-67144
Topics:
Fuel rods
,
Modeling
,
China
,
Computer software
,
Nuclear power
,
Nuclear reactors
Calculation of the Macroscopic Group Constant of Pebble Bed Fluoride Salt Cooled High Temperature Reactor Based on the Collision Probability Method
ICONE 2017; V003T02A045https://doi.org/10.1115/ICONE25-67194
Topics:
Collisions (Physics)
,
High temperature
,
Probability
,
Fuels
,
Generation IV reactors
,
Neutron flux
A Comparative Study of 10 Different Methods on Numerical Solving of Point Reactor Neutron Kinetics Equations
ICONE 2017; V003T02A049https://doi.org/10.1115/ICONE25-67275
Topics:
Neutrons
,
Errors
,
Polynomials
,
Runge-Kutta methods
,
Gears
,
Computer simulation
,
Density
,
Nuclear power stations
,
Nuclear reactors
,
Stiffness
The Rigorous SP3 Theory and Study on its Numerical Verification
ICONE 2017; V003T02A050https://doi.org/10.1115/ICONE25-67309
Topics:
Approximation
,
Boundary-value problems
,
Leakage
,
Scalars
Investigation Into the Influence of Fuel Rods on the Anti-Seismic Mechanical Characteristics of Fuel Assembly Spacer Grid by FEM Method
ICONE 2017; V003T02A052https://doi.org/10.1115/ICONE25-67362
Topics:
Finite element methods
,
Finite element model
,
Fuel rods
,
Fuels
,
Manufacturing
,
Mechanical properties
,
Springs
,
Deflection
,
Friction
,
Simulation
Diffusion of Fission Gas in Uranium Dioxide: A First-Principles Study
ICONE 2017; V003T02A053https://doi.org/10.1115/ICONE25-67365
Topics:
Diffusion (Physics)
,
Nuclear fission
,
Uranium
,
Oxygen
,
Atoms
,
Fuels
,
Computational methods
,
Density functional theory
,
Ductility
,
Elastic constants
Physics Design of Epi-Thermal Neutron Beam for BNCT Based on C-MNSR
ICONE 2017; V003T02A054https://doi.org/10.1115/ICONE25-67384
Topics:
Design
,
Neutron beams
,
Physics
,
Fuels
,
Neutrons
,
Cancer
,
Uranium
,
Boron
,
Contamination
,
Density
Composite Versus Dispersed Accident Tolerant Nuclear Fuels
ICONE 2017; V003T02A056https://doi.org/10.1115/ICONE25-67478
Topics:
Accidents
,
Composite materials
,
Nuclear fuels
,
Fuels
,
Temperature
,
Temperature gradient
,
Thermal conductivity
,
Aluminum
,
Approximation
,
Cracking (Materials)
Effect of Fuel Meat Thickness on the Non-Uniform Irradiation-Induced Thermo-Mechanical Behavior in Monolithic UMo/Al Fuel Plates
ICONE 2017; V003T02A057https://doi.org/10.1115/ICONE25-67531
Topics:
Fuels
,
Irradiation (Radiation exposure)
,
Plates (structures)
,
Thermomechanics
,
Stress
,
Algorithms
,
Constitutive equations
,
Deformation
,
Density
,
Design
A Research Reactor Core Design for Advance Neutron Source
ICONE 2017; V003T02A059https://doi.org/10.1115/ICONE25-67573
Topics:
Design
,
Neutron sources
,
Heat flux
,
Brightness (Photometry)
,
Cycles
,
Fuels
,
Neutrons
,
Thermal energy
Physical Design on PMNSR With LEU Core
ICONE 2017; V003T02A060https://doi.org/10.1115/ICONE25-67580
Topics:
Design
,
Fuels
,
Neutron flux
,
Uranium
,
Coolants
,
Engineering prototypes
,
Error analysis
,
Irradiation (Radiation exposure)
,
Manufacturing
,
Neutron sources
Study on Semi-Analytical Nodal Method for Solving SP3 Equation
ICONE 2017; V003T02A061https://doi.org/10.1115/ICONE25-67597
Topics:
Algebra
,
Diffusion (Physics)
,
Neutrons
,
Physics
,
Polynomials
Verifying Calculation of the Parameters of AP1000 Core Design Based on MCNP Model
Xiong Wen-bin, Yan Xiu-ping, Wang Bo, Wang Zhan-yong, Bie Ye-wang, Zhang Bo-ping, Yang Ming, Chen Ci, Cai Ning
ICONE 2017; V003T02A063https://doi.org/10.1115/ICONE25-67727
Topics:
Design
,
Nuclear power stations
,
Safety
The Effect of MA Transmutation in the PWR on Fuel Cycle
ICONE 2017; V003T02A065https://doi.org/10.1115/ICONE25-67787
Topics:
Nuclear fuel cycle
,
Pressurized water reactors
,
Rods
,
Nuclides
,
Spent nuclear fuels
Innovative Nuclear Power Plant Design and New Technology Application
Cycle Calculations of a Small-Scale Heat Removal System With Supercritical CO2 As Working Fluid
ICONE 2017; V003T13A001https://doi.org/10.1115/ICONE25-66084
Topics:
Cycles
,
Fluids
,
Heat
,
Supercritical carbon dioxide
,
Accidents
,
Brayton cycle
,
Design
,
Electricity (Physics)
,
Heat sinks
,
Glass
Development of NPP Collaborative Design Management Platform
ICONE 2017; V003T13A003https://doi.org/10.1115/ICONE25-66105
Topics:
Design
,
Nuclear power stations
,
Construction
,
Nuclear design
,
Optimization
Study on TlBr Radioactive Detector
ICONE 2017; V003T13A004https://doi.org/10.1115/ICONE25-66120
Topics:
Sensors
,
Resolution (Optics)
,
Atomic number
,
Density
,
Energy (Physics)
,
Energy gap
,
Engineering prototypes
,
Gamma rays
,
Inspection
,
Ionization energy
Application of the Burnable Poison in the Design of Space Nuclear Reactor
ICONE 2017; V003T13A006https://doi.org/10.1115/ICONE25-66393
Topics:
Design
,
Nuclear reactors
,
Gadolinium
,
Safety
,
Accidents
,
Neutrons
,
Europium
,
Samarium
Radioisotope Thermophotovoltaic Generator Design and Performance Estimates for Terrestrial Applications
ICONE 2017; V003T13A008https://doi.org/10.1115/ICONE25-66607
Topics:
Design
,
Generators
,
Radioisotopes
,
Energy conversion
,
Heat
,
Heat sinks
,
Insulation
,
Circuits
,
Crystals
,
Design methodology
Modeling and Simulating Supercritical CO2 Brayton Cycle in SMR Using Modelica
ICONE 2017; V003T13A009https://doi.org/10.1115/ICONE25-66649
Topics:
Brayton cycle
,
Modeling
,
Supercritical carbon dioxide
,
Carbon dioxide
,
Fluids
,
Pressure
,
Simulation
,
Temperature
,
Compression
,
Computer simulation
Small Modular Pressurized Water Reactors Combined With Conventional Thermal Power Plant
ICONE 2017; V003T13A010https://doi.org/10.1115/ICONE25-66690
Topics:
Pressurized water reactors
,
Thermal power stations
,
Hybrid power systems
,
Steam
,
Superheating
,
Boilers
,
Nuclear power
,
Carbon
,
Coal
,
Emissions
Load Following by Cogeneration: Options for Small Modular Reactors, GEN IV Reactor and Traditional Large Plants
ICONE 2017; V003T13A013https://doi.org/10.1115/ICONE25-67180
Topics:
Combined heat and power
,
Small modular reactors
,
Stress
,
Nuclear power stations
,
Electricity (Physics)
,
Water
,
Circuits
,
Diesel
,
Fuels
,
Hydrogen
Optical Readout Characteristics in a New Gas Scintillation Chamber for Neutron Measurement
ICONE 2017; V003T13A014https://doi.org/10.1115/ICONE25-67249
Topics:
Neutrons
,
Signals
,
Electric fields
,
Wire
,
Particulate matter
,
Electrons
,
Gases
,
Photons
,
Protons
,
Resolution (Optics)
Email alerts
Most Read Proceedings Papers in ICONE
ICONE31 Front Matter
ICONE31