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2013 21st International Conference on Nuclear Engineering

July 29–August 2, 2013

Chengdu, China

Conference Sponsors:

ISBN:

978-0-7918-5579-9

In This Volume

Plant Systems, Construction, Structures and Components (59)
Next Generation Reactors and Advanced Reactors (78)

Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors

Plant Systems, Construction, Structures and Components

Design Development of a Nuclear Standard Bidirectional Solenoid Valve to Enable PWR Fluid System Simplification

Chris Mann

ICONE 2013; V002T03A001https://doi.org/10.1115/ICONE21-15112

Abstract

View Articletitled, Design Development of a Nuclear Standard Bidirectional Solenoid Valve to Enable PWR Fluid System Simplification

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Topics: Design , Fluids , Pressurized water reactors , Solenoids , Valves , Water , Maintenance , Petrochemicals , Pneumatic control valves , Pneumatic systems

Researches on the Simulation of the Degasifying Column Used in Nuclear Power Plant

Jianhua Xie, Quanliu Ye, Jinchun Yang

ICONE 2013; V002T03A002https://doi.org/10.1115/ICONE21-15113

Abstract

View Articletitled, Researches on the Simulation of the Degasifying Column Used in Nuclear Power Plant

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Topics: Nuclear power stations , Simulation , Computer software , Nuclear reactor coolants , Oxygen , Process simulation , Risk , Simulation results

Experimental Investigations of Control Rod Drive Mechanism

Guangyao Lu, Zhaohui Lu, Wenyuan Xiang, Yonghong Lv, Wenyou Huang, Jianming Zhou

ICONE 2013; V002T03A003https://doi.org/10.1115/ICONE21-15196

Abstract

View Articletitled, Experimental Investigations of Control Rod Drive Mechanism

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Topics: Accidents , China , Design , Nuclear power , Nuclear power stations , Nuclear reactors , Pressurized water reactors , Reactor vessels , Rods , Signals

Study on the Prestressing Effect in Reinforced Concrete Containment by Using ANSYS

Feng Sun, Rong Pan

ICONE 2013; V002T03A004https://doi.org/10.1115/ICONE21-15241

Abstract

View Articletitled, Study on the Prestressing Effect in Reinforced Concrete Containment by Using ANSYS

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Topics: Containment , Design , Pressure , Reinforced concrete , Tendons

Sensitivity Analysis and Design Improvement of Contra-Motion Check Valve

Zhi-da Yang, Bing-de Chen, Wei Huang, Wei-shi Han

ICONE 2013; V002T03A005https://doi.org/10.1115/ICONE21-15276

Abstract

View Articletitled, Sensitivity Analysis and Design Improvement of Contra-Motion Check Valve

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Topics: Design , Sensitivity analysis , Valves , Flow (Dynamics) , Pistons , Pressure , Damping , Disks , Fluids , Leakage

Elementary Analysis for the Decommissioning Schedule of High Temperature Reactors

Yin Xiong, Shengqiang Li, Yalei Hao, Shengyao Jiang

ICONE 2013; V002T03A006https://doi.org/10.1115/ICONE21-15287

Abstract

View Articletitled, Elementary Analysis for the Decommissioning Schedule of High Temperature Reactors

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Topics: High temperature , Nuclear decommissioning , Safety

Elementary Analysis of the Quality Assurance for Probabilistic Safety Analysis

Yin Xiong, Shengqiang Li, Yalei Hao, Shengyao Jiang

ICONE 2013; V002T03A007https://doi.org/10.1115/ICONE21-15288

Abstract

View Articletitled, Elementary Analysis of the Quality Assurance for Probabilistic Safety Analysis

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Topics: Probabilistic safety assessment , Quality control , Accounting , Nuclear power stations , Probabilistic risk assessment , Project management , Regulations , Security , Uncertainty

Study of Graphite Dust Releasing Behavior in a Depressurization Accident of HTR

Wei Peng, Ya-nan Zhen, Xiao-yong Yang, Su-yuan Yu

ICONE 2013; V002T03A008https://doi.org/10.1115/ICONE21-15324

Abstract

View Articletitled, Study of Graphite Dust Releasing Behavior in a Depressurization Accident of HTR

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Topics: Accidents , Dust , Graphite , Helium , Fuels , Boilers , Circuits , Contamination , Coolants , Flow (Dynamics)

Experimental Study on Adsorption of Carbon Dioxide on 13X Molecular Sieve for Coolant Helium Purification

Hua Chang, Tao Ma, Ling Liu, Hua-Qiang Yin, Xue-Dong He

ICONE 2013; V002T03A009https://doi.org/10.1115/ICONE21-15362

Abstract

View Articletitled, Experimental Study on Adsorption of Carbon Dioxide on 13X Molecular Sieve for Coolant Helium Purification

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Topics: Carbon dioxide , Coolants , Helium , Very high temperature reactors , Enthalpy , Equilibrium (Physics) , Mass transfer , Pressure , Roads , Temperature

Very Slow Pebble Flow: A New Research Field

Shengyao Jiang, Xingtuan Yang, Nan Gui, Jiyuan Tu

ICONE 2013; V002T03A010https://doi.org/10.1115/ICONE21-15370

Abstract

View Articletitled, Very Slow Pebble Flow: A New Research Field

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Topics: Flow (Dynamics)

Experimental and Numerical Study of the Movement Mechanism and Characteristics of the Quasi-Static Pebble Flow

Xinlong Jia, Nan Gui, Xingtuan Yang, Jiyuan Tu, Shengyao Jiang

ICONE 2013; V002T03A011https://doi.org/10.1115/ICONE21-15371

Abstract

View Articletitled, Experimental and Numerical Study of the Movement Mechanism and Characteristics of the Quasi-Static Pebble Flow

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Topics: Discrete element methods , Flow (Dynamics)

Experimental Research and DEM Simulations on Stagnant Region in Pebble Bed Reactor

Yu Li, Nan Gui, Xingtuan Yang, Jiyuan Tu, Shengyao Jiang

ICONE 2013; V002T03A012https://doi.org/10.1115/ICONE21-15372

Abstract

View Articletitled, Experimental Research and DEM Simulations on Stagnant Region in Pebble Bed Reactor

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Topics: Discrete element methods , Engineering simulation , Simulation

Analysis of Fatigue Life for Main Steam Isolation Valve in Nuclear Power Plants

Xian Zeng, Hong Xia, YeMin Dong, Zhen Liu

ICONE 2013; V002T03A013https://doi.org/10.1115/ICONE21-15387

Abstract

View Articletitled, Analysis of Fatigue Life for Main Steam Isolation Valve in Nuclear Power Plants

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Topics: Fatigue , Fatigue analysis , Fatigue life , Nuclear power stations , Steam , Valves

Several Constraint Methods for Avoiding Thermal Stress Distortion on Structure Simulating Calculation

Shoutong Dai, Hao Yin

ICONE 2013; V002T03A014https://doi.org/10.1115/ICONE21-15405

Abstract

View Articletitled, Several Constraint Methods for Avoiding Thermal Stress Distortion on Structure Simulating Calculation

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Topics: Thermal stresses

Theoretic Analysis on Separation Efficiency of Wire Mesh Mist Eliminator of High-Temperature Gas-Cooled Reactor Helium Purification and Auxiliary System

Huaqiang Yin, Lei Hao, Xingtuan Yang, Xuedong He

ICONE 2013; V002T03A015https://doi.org/10.1115/ICONE21-15417

Abstract

View Articletitled, Theoretic Analysis on Separation Efficiency of Wire Mesh Mist Eliminator of High-Temperature Gas-Cooled Reactor Helium Purification and Auxiliary System

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Topics: Helium , Separation (Technology) , Theoretical analysis , Very high temperature reactors , Wire mesh , Accidents , Fluids , Packing (Shipments) , Packings (Cushioning) , Systems engineering

Prospective Applications of Flow Drag and Noise Reduction Technology for Nuclear Reactors

Beibei Feng, Darong Chen, Xingtuan Yang, Shengyao Jiang

ICONE 2013; V002T03A016https://doi.org/10.1115/ICONE21-15427

Abstract

View Articletitled, Prospective Applications of Flow Drag and Noise Reduction Technology for Nuclear Reactors

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Topics: Drag (Fluid dynamics) , Flow (Dynamics) , Noise control , Nuclear reactors , Cooling , Helium , Noise (Sound) , Water , Engineering systems and industry applications , Heat transfer

Evaluation of Interaction Effects on Part-Through Cracks in Steam Generator Tubes

Yong-Seok Kang, Hong-Deok Kim, Kuk-Hee Lee, Jai-Hak Park

ICONE 2013; V002T03A017https://doi.org/10.1115/ICONE21-15429

Abstract

View Articletitled, Evaluation of Interaction Effects on Part-Through Cracks in Steam Generator Tubes

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Topics: Boilers , Fracture (Materials) , Pressure

Effect of Feeder Inner Structure on Feeding Performance for Absorber Sphere Pneumatic Conveying

Tianjin Li, Feng Chen, He Zhang, Hairui Yang, Zhiyong Huang, Hanliang Bo, He Yan, WeiWei Qi

ICONE 2013; V002T03A018https://doi.org/10.1115/ICONE21-15431

Abstract

View Articletitled, Effect of Feeder Inner Structure on Feeding Performance for Absorber Sphere Pneumatic Conveying

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Topics: Design , Flow (Dynamics) , Fluidization , Glass , Optimization , Pressure

Prospect of MAO Technology Application in Nuclear Power Industry

Zheng Zhao, Beibei Feng, Xingtuan Yang, Yanfei Sun

ICONE 2013; V002T03A019https://doi.org/10.1115/ICONE21-15435

Abstract

View Articletitled, Prospect of MAO Technology Application in Nuclear Power Industry

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Topics: Nuclear industry , Alloys , Aluminum , Cladding systems (Building) , Corrosion , Fuels , Nuclear reactors , Accidents , Aerospace industry , Aviation

Theoretical Analysis of a Natural Circulation System Under Rolling Condition Based on RELAP5/MOD3.3 Code

Haibo Lian, Hongye Zhu, Xingtuan Yang, Shengyao Jiang

ICONE 2013; V002T03A020https://doi.org/10.1115/ICONE21-15441

Abstract

View Articletitled, Theoretical Analysis of a Natural Circulation System Under Rolling Condition Based on RELAP5/MOD3.3 Code

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Topics: Circuits , Flow (Dynamics) , Heat , Ships , Symmetry (Physics) , Theoretical analysis

Experimental and Numerical Study on Natural Circulation Under Inclined Condition

Hongye Zhu, Xingtuan Yang, Haibo Lian, Shengyao Jiang

ICONE 2013; V002T03A021https://doi.org/10.1115/ICONE21-15444

Abstract

View Articletitled, Experimental and Numerical Study on Natural Circulation Under Inclined Condition

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Topics: Accidents , Circuits , Computational fluid dynamics , Design , Flow (Dynamics) , Numerical analysis , Thermal hydraulics

Transient Analysis of Active Residual Heat Removal Process for HTR-PM

Hongye Zhu, Xingtuan Yang, Huaiming Ju, Shengyao Jiang

ICONE 2013; V002T03A022https://doi.org/10.1115/ICONE21-15448

Abstract

View Articletitled, Transient Analysis of Active Residual Heat Removal Process for HTR-PM

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Topics: Heat , Transient analysis , Boilers , Helium , Coolants , Shock (Mechanics) , Boiling , Flow (Dynamics) , Stress , China

Experimental Study of Magnetic Synchronizator in HTR-PM Fuel Handling System

Haiquan Zhang, Xin Wang, Junfeng Nie, Hongke Li, Jiguo Liu, Xuelan Yan, Kezhong Zhao

ICONE 2013; V002T03A023https://doi.org/10.1115/ICONE21-15477

Abstract

View Articletitled, Experimental Study of Magnetic Synchronizator in HTR-PM Fuel Handling System

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Topics: Fuels , Bearings , Reliability , Lubrication , Magnets , Radiation (Physics) , Rotors , Test facilities , Engineers , Heat

A Numerical Study of Eccentricity Effect to Heat Transfer Under Single Phase Force Convection Inside a Vertical Annulus

Yang Liu, Qianqian Jia, Haijun Jia

ICONE 2013; V002T03A024https://doi.org/10.1115/ICONE21-15510

Abstract

View Articletitled, A Numerical Study of Eccentricity Effect to Heat Transfer Under Single Phase Force Convection Inside a Vertical Annulus

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Topics: Annulus , Convection , Heat transfer , Numerical analysis

Falling Characteristic Analysis of Passive Drive Mechanism of Absorber Ball Shutdown System for HTR-PM

Feng Chen, Tianjin Li, Yuan Liu, Zhiyong Huang, Hanliang Bo

ICONE 2013; V002T03A025https://doi.org/10.1115/ICONE21-15511

Abstract

View Articletitled, Falling Characteristic Analysis of Passive Drive Mechanism of Absorber Ball Shutdown System for HTR-PM

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Topics: Design , Gravity (Force) , Heating , Nuclear reactors , Reliability , Safety , Storage , Temperature , Valves , Vessels

Thermal Analysis of the Head of the Direct Action Solenoid Valve

Qian-feng Liu, Han-liang Bo

ICONE 2013; V002T03A026https://doi.org/10.1115/ICONE21-15555

Abstract

View Articletitled, Thermal Analysis of the Head of the Direct Action Solenoid Valve

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Topics: Hydraulic drive systems , Solenoids , Thermal analysis , Valves

The Impact of the High Temperature on the Performance of Critical Components in the HTR-PM Control Rod Drive Mechanism

Cheng Chen, Xingzhong Diao

ICONE 2013; V002T03A027https://doi.org/10.1115/ICONE21-15559

Abstract

View Articletitled, The Impact of the High Temperature on the Performance of Critical Components in the HTR-PM Control Rod Drive Mechanism

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Topics: Dampers , High temperature , Permanent magnets , Stepper motors , Temperature , Emergencies , Engines , Mechanical properties , Motors , Reliability

The Reliability Prediction of HTR’s Graphite Component in Various Temperature and Neutron Dose Levels

Xiang Fang, Haitao Wang, Xingtuan Yang, Suyuan Yu

ICONE 2013; V002T03A028https://doi.org/10.1115/ICONE21-15574

Abstract

View Articletitled, The Reliability Prediction of HTR’s Graphite Component in Various Temperature and Neutron Dose Levels

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Topics: Graphite , Neutrons , Reliability , Temperature , Bricks , High temperature , Irradiation (Radiation exposure) , Stress , Constitutive equations , Failure

Results and Discussion on Scaling Analysis for the NHR200-II Integral Test Facility Under Single Phase Natural Circulation

Yang Liu, Qianqian Jia, Haijun Jia, Lei Wu

ICONE 2013; V002T03A029https://doi.org/10.1115/ICONE21-15659

Abstract

View Articletitled, Results and Discussion on Scaling Analysis for the NHR200-II Integral Test Facility Under Single Phase Natural Circulation

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Topics: Test facilities , Fluids , Density , Engineering prototypes , Flow (Dynamics) , Heat flux , Heating , Pressure , Seawater , Steam

Numerical Study of the Gas-Steam Transient Behavior in the Integrated Pressurizer

Lei Wu, Haijun Jia, Yang Liu

ICONE 2013; V002T03A030https://doi.org/10.1115/ICONE21-15660

Abstract

View Articletitled, Numerical Study of the Gas-Steam Transient Behavior in the Integrated Pressurizer

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Topics: Steam , Transients (Dynamics) , Pressure , Heating , Temperature , Boiling , High temperature , Nitrogen , Plasma spraying , Safety

Magnetic Field Analysis of Active Magnetic Bearings for Helium Blower of HTR-PM

Leilei Guo, Guojun Yang, Zhengang Shi, Xingnan Liu, Suyuan Yu

ICONE 2013; V002T03A031https://doi.org/10.1115/ICONE21-15669

Abstract

View Articletitled, Magnetic Field Analysis of Active Magnetic Bearings for Helium Blower of HTR-PM

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Topics: Helium , Magnetic bearings , Magnetic fields , Design , Manufacturing , Rotors , Stress , Bearings , China , Clearances (Engineering)

Design of Moderators and Reflectors for Chinese Spallation Neutron Source

Wenting Du, Chunming Hu, Chaoju Yu, Jianfei Tong

ICONE 2013; V002T03A032https://doi.org/10.1115/ICONE21-15797

Abstract

View Articletitled, Design of Moderators and Reflectors for Chinese Spallation Neutron Source

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Topics: Design , Neutron sources , Optical mirrors , Spallation (Nuclear physics) , Hydrogen , Vessels , Aluminum alloys , Containers , Dynamics (Mechanics) , Education

Seismic Response Spectrum Analysis on Advanced PWR Coolant System

Rong Duan, Lili Tong, Xuewu Cao

ICONE 2013; V002T03A033https://doi.org/10.1115/ICONE21-15825

Abstract

View Articletitled, Seismic Response Spectrum Analysis on Advanced PWR Coolant System

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Topics: Coolants , Emission spectroscopy , Pressurized water reactors , Spectroscopy , Stress , Earthquakes , Boilers , Design , Pressure , Pumps

The Fracture Behavior of Cylinders With Axial Surface Cracks Under Strong Through-Wall Bending Stresses

Yuebing Li, Zengliang Gao, Yuebao Lei

ICONE 2013; V002T03A034https://doi.org/10.1115/ICONE21-15868

Abstract

View Articletitled, The Fracture Behavior of Cylinders With Axial Surface Cracks Under Strong Through-Wall Bending Stresses

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Topics: Bending (Stress) , Cylinders , Fracture (Materials) , Surface cracks , Thermal shock

A Three-Dimensional Rigid-Body Model for Seismic Analysis of the Pebble-Bed HTR Graphite Core Structure

Chuan Zeng, Haitao Wang

ICONE 2013; V002T03A035https://doi.org/10.1115/ICONE21-15896

Abstract

View Articletitled, A Three-Dimensional Rigid-Body Model for Seismic Analysis of the Pebble-Bed HTR Graphite Core Structure

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Topics: Graphite , Seismic analysis , Bricks , Shapes , Stress , Center of mass , Collisions (Physics) , Computers , Degrees of freedom , Dynamic analysis

Study on Comparison Between Inconel 617 and GH3128 as Structural Material Candidates for Intermediate Heat Exchanger

Yunbai Shi, Kun Yuan, Xi Zhao, Yannan Wu

ICONE 2013; V002T03A036https://doi.org/10.1115/ICONE21-15948

Abstract

View Articletitled, Study on Comparison Between Inconel 617 and GH3128 as Structural Material Candidates for Intermediate Heat Exchanger

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Topics: Heat exchangers , Alloys , Heat , High temperature , Nickel , Very high temperature reactors , China , Creep , Temperature , Tensile strength

Structure Design of Jordan Subcritical Reactor

Chengzhi Yao, Yuerong Fan, Jinshan Zhang, Haifen Han, Dayong Yi, Zhanli Zhang

ICONE 2013; V002T03A037https://doi.org/10.1115/ICONE21-15971

Abstract

View Articletitled, Structure Design of Jordan Subcritical Reactor

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Topics: Design , Neutron sources , Teaching , Testing , Water , Chain , Fuels , Industrial research , Machining , Manufacturing

Interference Fit Design for Rotor Components of the Active Magnetic Bearing

Xingnan Liu, Guojun Yang, Yang Xu, Yue Li, Zhengang Shi, Suyuan Yu

ICONE 2013; V002T03A038https://doi.org/10.1115/ICONE21-16016

Abstract

View Articletitled, Interference Fit Design for Rotor Components of the Active Magnetic Bearing

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Topics: Design , Magnetic bearings , Press fits , Rotors , Bearings , Centrifugal force , Electromagnetic force , Finite element analysis , Helium , High temperature

Circularity Error Analysis of Axial Displacement Sensor Detecting Surface for Active Magnetic Bearings of 10MW High Temperature Gas-Cooled Reactor (HTR-10GT)

Jingjing Zhao, Yan Zhou, Zhe Sun, Suyuan Yu

ICONE 2013; V002T03A039https://doi.org/10.1115/ICONE21-16098

Abstract

View Articletitled, Circularity Error Analysis of Axial Displacement Sensor Detecting Surface for Active Magnetic Bearings of 10MW High Temperature Gas-Cooled Reactor (HTR-10GT)

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Topics: Displacement , Error analysis , Magnetic bearings , Sensors , Very high temperature reactors , Rotors , Errors , China , Compressors , Degrees of freedom

Experimental Study of a Gas Separator for MSR Gas Removal System

Nana Zhang, Changqi Yan, Licheng Sun

ICONE 2013; V002T03A040https://doi.org/10.1115/ICONE21-16124

Abstract

View Articletitled, Experimental Study of a Gas Separator for MSR Gas Removal System

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Topics: Molten salt reactors , Separation (Technology) , Water , Pressure drop , Flow (Dynamics) , Breeder reactors , Bubbles , Conceptual design , Design , Fluids

The Position Design for M310 Reactor Vessel’s Instrumentation Penetration Based on None-Alignment Analysis

Xin Xia, Hua Du, Ning Li, Bin Xu, Yan Li, Wei Zhao

ICONE 2013; V002T03A041https://doi.org/10.1115/ICONE21-16177

Abstract

View Articletitled, The Position Design for M310 Reactor Vessel’s Instrumentation Penetration Based on None-Alignment Analysis

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Topics: Design , Instrumentation

Research of the Effects on a Nuclear Cable Material Irradiated by Beta/Gamma Irradiation

Weixia Zhong, Jiansheng Sun, Jinping Liu, Ping Sun

ICONE 2013; V002T03A042https://doi.org/10.1115/ICONE21-16198

Abstract

View Articletitled, Research of the Effects on a Nuclear Cable Material Irradiated by Beta/Gamma Irradiation

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Topics: Cables , Gamma rays , Irradiation (Radiation exposure)

Identification of Flexible Rotor Suspended by Magnetic Bearings

Zhe Sun, Jingjing Zhao, Zhengang Shi, Suyuan Yu

ICONE 2013; V002T03A043https://doi.org/10.1115/ICONE21-16220

Abstract

View Articletitled, Identification of Flexible Rotor Suspended by Magnetic Bearings

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Topics: Magnetic bearings , Rotors , Bearings , Stiffness , Very high temperature reactors , Degrees of freedom , Design , Force sensors , Helium

Experimental Investigation of Non Stationary Heat Transfer Between Fluid and Solid Body

Jerzy Marcinkiewicz, Jan Taler, Artur Cebula

ICONE 2013; V002T03A044https://doi.org/10.1115/ICONE21-16253

Abstract

View Articletitled, Experimental Investigation of Non Stationary Heat Transfer Between Fluid and Solid Body

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Topics: Fluids , Heat transfer , Computational fluid dynamics , Damage , Heat flux , Computers , Errors , Temperature , Temperature measurement , Thermocouples

Experiment Study on Collision of Graphite Dowel-Brick Structures

Lie Jin, Libin Sun, Hongtao Wang, Haitao Wang, Xinxin Wu, Shaopeng Ma

ICONE 2013; V002T03A045https://doi.org/10.1115/ICONE21-16283

Abstract

View Articletitled, Experiment Study on Collision of Graphite Dowel-Brick Structures

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Topics: Bricks , Collisions (Physics) , Graphite

Stress Analysis and Assess for Nuclear Pipes of Class 1 Based on PIPESTRESS

Rui Liu, Tie-ping Li, Ming-yu Wang

ICONE 2013; V002T03A046https://doi.org/10.1115/ICONE21-16313

Abstract

View Articletitled, Stress Analysis and Assess for Nuclear Pipes of Class 1 Based on PIPESTRESS

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Topics: Pipes , Stress analysis (Engineering) , Computer software , Coolants , Cooling , Fatigue analysis , Finite element analysis , High pressure (Physics) , High temperature , Nuclear power

Electromagnetic Self-Locking Device for Air Cylinders in Spent Fuel Storage System of Pebble-Bed High Temperature Gas-Cooled Reactor

Bin Wu, Jinhua Wang, Yue Li, Jiguo Liu

ICONE 2013; V002T03A047https://doi.org/10.1115/ICONE21-16342

Abstract

View Articletitled, Electromagnetic Self-Locking Device for Air Cylinders in Spent Fuel Storage System of Pebble-Bed High Temperature Gas-Cooled Reactor

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Topics: Pneumatic cylinders , Spent fuel storage , Very high temperature reactors , Locks (Waterways) , Compressed air , Cylinders , Machinery , Spent nuclear fuels , Temperature , Accidents

Assessing the Design Margins for an Ultimate Heat Sink Sizing

Dong Zheng, Julie M. Jarvis, Allen T. Vieira

ICONE 2013; V002T03A048https://doi.org/10.1115/ICONE21-16396

Abstract

View Articletitled, Assessing the Design Margins for an Ultimate Heat Sink Sizing

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Topics: Cooling towers , Design , Heat sinks , Meteorology

The Optimization Design of Lower Plenum and Distribution Plates in MSR

Jianjun Zhou, Suizheng Qiu, Zhangpeng Guo, Guanghui Su

ICONE 2013; V002T03A049https://doi.org/10.1115/ICONE21-16436

Abstract

View Articletitled, The Optimization Design of Lower Plenum and Distribution Plates in MSR

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Topics: Design , Molten salt reactors , Optimization , Plates (structures) , Flow (Dynamics) , Fuels , Coolants , Computational fluid dynamics , Computer software , Generation IV reactors

On Efficient Passive Cooling of Control Rod Drivers

A. N. Gershuni, A. P. Nishchik, V. G. Razumovskiy, I. L. Pioro

ICONE 2013; V002T03A050https://doi.org/10.1115/ICONE21-16449

Abstract

View Articletitled, On Efficient Passive Cooling of Control Rod Drivers

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Topics: Cooling , Natural convection , Reactor protection systems , Cooling systems , Heat transfer , Circuits , Condensation , Coolants , Design , Evaporation

Nonlinear Crest-Cut-Off Method for Reducing the Stress Concentration of Bolt With Many Threads: Application in the Main Bolt of HTGR’s RPV

Jiaqing Zhao, Zhengming Zhang

ICONE 2013; V002T03A051https://doi.org/10.1115/ICONE21-16457

Abstract

View Articletitled, Nonlinear Crest-Cut-Off Method for Reducing the Stress Concentration of Bolt With Many Threads: Application in the Main Bolt of HTGR’s RPV

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Topics: Stress concentration , Thread , Stress , Computer simulation , Degrees of freedom , Design , Finite element analysis , High temperature , Polynomials , Reactor vessels

Research and Solution on Vibration and Noise Caused by Orifice Cavitations of PTR System

Ting Yang, Yao Dong Wang, Xu Lun Jiang, Chun Ming Wu

ICONE 2013; V002T03A052https://doi.org/10.1115/ICONE21-16474

Abstract

View Articletitled, Research and Solution on Vibration and Noise Caused by Orifice Cavitations of PTR System

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Topics: Noise (Sound) , Vibration , Cooling , Orifices , Cavities , Design , Nuclear power stations , Pipes , Pressure drop , Redundancy (Engineering)

Scientific Bases of Water Chemistry for Corrosion Control of NPPs by Integration of Radiation- and Electro-Chemistry

Genn Saji

ICONE 2013; V002T03A053https://doi.org/10.1115/ICONE21-16525

Abstract

View Articletitled, Scientific Bases of Water Chemistry for Corrosion Control of NPPs by Integration of Radiation- and Electro-Chemistry

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Topics: Corrosion , Corrosion protection , Electrochemistry , Nuclear power stations , Radiation (Physics) , Water , Water chemistry

Analyzing and Comparing the Floor Response Spectra of the NPP Based on Different Soil Dynamic Numerical Models

Xiu-yun Zhu, Rong Pan

ICONE 2013; V002T03A054https://doi.org/10.1115/ICONE21-16627

Abstract

View Articletitled, Analyzing and Comparing the Floor Response Spectra of the NPP Based on Different Soil Dynamic Numerical Models

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Topics: Computer simulation , Nuclear power stations , Soil , Spectra (Spectroscopy)

Shaking Table Tests and Numerical Simulation Analysis of a 1:15 Scale Model Reinforced Concrete Containment Vessel

Xiaolei Wang, Dagang Lu, Gangling Hou

ICONE 2013; V002T03A055https://doi.org/10.1115/ICONE21-16668

Abstract

View Articletitled, Shaking Table Tests and Numerical Simulation Analysis of a 1:15 Scale Model Reinforced Concrete Containment Vessel

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Topics: Computer simulation , Containment vessels , Reinforced concrete , Earthquakes , Excitation , Cracking (Materials) , Cylinders , Design , Displacement , Engineering prototypes

Comparative Study on Self-Compacting Concrete Pouring Methods of AP1000 Structure Module

Shuai Dai, Zhonghao Ye, Erfei Li, Chuyao Zheng

ICONE 2013; V002T03A056https://doi.org/10.1115/ICONE21-16823

Abstract

View Articletitled, Comparative Study on Self-Compacting Concrete Pouring Methods of AP1000 Structure Module

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Topics: Compacting , Concrete placement , Concretes , Construction , Modular construction

Preliminary Study of Graphite Dust Resuspension in Steam Generator of HTR-10

Tianqi Zhang, Wei Peng, Qijia Yang, Suyuan Yu

ICONE 2013; V002T03A057https://doi.org/10.1115/ICONE21-16839

Abstract

View Articletitled, Preliminary Study of Graphite Dust Resuspension in Steam Generator of HTR-10

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Topics: Boilers , Dust , Graphite , Very high temperature reactors

The Application of Virtual Reality Technology to the Conical Roof Lifting for the AP1000 Nuclear Power Plant

Yang Shen, Hongwei Shen

ICONE 2013; V002T03A058https://doi.org/10.1115/ICONE21-16863

Abstract

View Articletitled, The Application of Virtual Reality Technology to the Conical Roof Lifting for the AP1000 Nuclear Power Plant

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Topics: Cranes , Nuclear power stations , Roofs , Virtual reality

Ventilation Management for the AP1000 Containment Building During Construction Stage

Zhiyou Sun, Hongwei Shen

ICONE 2013; V002T03A059https://doi.org/10.1115/ICONE21-16864

Abstract

View Articletitled, Ventilation Management for the AP1000 Containment Building During Construction Stage

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Topics: Construction , Containment buildings , Ventilation , Risk , Safety , Accidents , Fume control , Gases , Oxygen

Next Generation Reactors and Advanced Reactors

On the Applicability of Pool Boiling Models in TRACE for the Evaluation of a Counter-Current LBE-Water Heat Exchanger

Wadim Jaeger, Victor Hugo Sánchez Espinoza

ICONE 2013; V002T05A001https://doi.org/10.1115/ICONE21-15081

Abstract

View Articletitled, On the Applicability of Pool Boiling Models in TRACE for the Evaluation of a Counter-Current LBE-Water Heat Exchanger

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Topics: Heat exchangers , Pool boiling , Water , Heat flux , Heat transfer coefficients , Boundary-value problems , Coolants , Design , Heat transfer , Light water reactors

A Study on SCWR Core Design and Fuel Management

Yong Zhang, Jue Yang, Dongsheng Li, Liangzhi Cao, Fei Wang, Shuai Zhao, Hongbo Li

ICONE 2013; V002T05A002https://doi.org/10.1115/ICONE21-15083

Abstract

View Articletitled, A Study on SCWR Core Design and Fuel Management

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Topics: Design , Fuel management , Supercritical water reactors , Equilibrium (Physics) , Fuel rods , Temperature , Coolants , Cycles , Manufacturing , Cladding systems (Building)

Scaling for Different Containment Passive Cooling Design Under LOCA Conditions

Shengqiang Li, Yin Xiong, Yalei Hao, Shengyao Jiang

ICONE 2013; V002T05A003https://doi.org/10.1115/ICONE21-15143

Abstract

View Articletitled, Scaling for Different Containment Passive Cooling Design Under LOCA Conditions

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Topics: Containment , Cooling , Design , Pressurized water reactors , Test facilities , Water , Construction , Cooling systems , Flow (Dynamics) , Heat

A New Design for SCWR Fuel Assemblies

Donghua Lu, Jue Yang, Qianhua Su, Qinglong Wen

ICONE 2013; V002T05A004https://doi.org/10.1115/ICONE21-15211

Abstract

View Articletitled, A New Design for SCWR Fuel Assemblies

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Topics: Design , Fuels , Supercritical water reactors , Rods , Water , Computational fluid dynamics , Fuel rods , Cladding systems (Building) , Heat transfer , Temperature

Hybrid Feedforward and Feedback Control of Steam Temperature in a Once-Through Direct Cycle Canadian SCWR

Peiwei Sun, Jianmin Zhang

ICONE 2013; V002T05A005https://doi.org/10.1115/ICONE21-15232

Abstract

View Articletitled, Hybrid Feedforward and Feedback Control of Steam Temperature in a Once-Through Direct Cycle Canadian SCWR

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Topics: Cycles , Feedback , Feedforward control , Steam , Supercritical water reactors , Temperature , Dynamic models , Control equipment , Control systems , Water

A Conceptual Design of a Small Modular Natural-Circulation Liquid Metal Fast Reactor With AMTEC Units

Xun Zhang, Daogang Lu

ICONE 2013; V002T05A006https://doi.org/10.1115/ICONE21-15235

Abstract

View Articletitled, A Conceptual Design of a Small Modular Natural-Circulation Liquid Metal Fast Reactor With AMTEC Units

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Topics: Conceptual design , Liquid metal cooled reactors , Design , Heat , Power conversion systems , Alkali metals , Construction , Distributed power generation , Energy conversion , Heat exchangers

The Treatment Technology of Radioactive Sodium in the Frame of Fast Reactors Decommissioning

Guozhi Wang, Haiou Du, Chun Xie, Rongdong Wang, Chen Liu

ICONE 2013; V002T05A007https://doi.org/10.1115/ICONE21-15240

Abstract

View Articletitled, The Treatment Technology of Radioactive Sodium in the Frame of Fast Reactors Decommissioning

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Topics: Fast neutron reactors , Nuclear decommissioning , Sodium , Coolants , Hazards , Sodium fast reactors

Thermal-Hydraulic Conceptual Design of Water-Cooled Blanket of a Fusion-Fission Hybrid Reactor for Energy Production

Haibing Guo, Xianjue Peng, Xueming Shi, Jimin Ma

ICONE 2013; V002T05A008https://doi.org/10.1115/ICONE21-15416

Abstract

View Articletitled, Thermal-Hydraulic Conceptual Design of Water-Cooled Blanket of a Fusion-Fission Hybrid Reactor for Energy Production

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Topics: Conceptual design , Energy generation , Nuclear fission , Water , Coolants , Fuels , Neutrons , Alloys , Computational fluid dynamics , Design

First-Principles Study of Mechanical Property and Electronic Structure of Quenching and Aging U-Ti Alloy

Jianbo Qi, Hong Guo, Guangxin Wu, Jieyu Zhang, Kuochih Chou

ICONE 2013; V002T05A009https://doi.org/10.1115/ICONE21-15440

Abstract

View Articletitled, First-Principles Study of Mechanical Property and Electronic Structure of Quenching and Aging U-Ti Alloy

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Topics: Alloys , Electron configuration , Mechanical properties , Quenching (Metalworking) , Tensile strength , Uranium , Elastic moduli , Solid solutions , Titanium , Adhesion

Self-Breeding and Radiotoxicity Analysis on Thorium-Based Molten Salt Reactors

Chun-yan Zou, Jin-gen Chen, Xiang-zhou Cai, Cheng-gang Yu, Da-zhen Jiang, Wei Guo, Yang Zou, Xiao-han Yu, Kun Chen

ICONE 2013; V002T05A010https://doi.org/10.1115/ICONE21-15454

Abstract

View Articletitled, Self-Breeding and Radiotoxicity Analysis on Thorium-Based Molten Salt Reactors

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Topics: Molten salt reactors , Nuclear fuel cycle , Fuels , Generation IV reactors , Nuclear power , Radioactive wastes , Sustainability

Research on the Stainless Steel Tubes and Pipes Material Standards of Demonstration Fast Reactor Power Plant

Yaping Li, Guangdong Song

ICONE 2013; V002T05A011https://doi.org/10.1115/ICONE21-15503

Abstract

View Articletitled, Research on the Stainless Steel Tubes and Pipes Material Standards of Demonstration Fast Reactor Power Plant

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Topics: Fast neutron reactors , Pipes , Power stations , Stainless steel , Construction , High temperature , Sodium , Engineering design , High pressure (Physics) , Liquid metals

Scaling Analysis of Liquid Lead–Bismuth Eutectic Thermal Stratification in ADS Facility Under LOCA

Ziwei Su, Tao Zhou, Yunbo Li, Yican Wu

ICONE 2013; V002T05A012https://doi.org/10.1115/ICONE21-15572

Abstract

View Articletitled, Scaling Analysis of Liquid Lead–Bismuth Eutectic Thermal Stratification in ADS Facility Under LOCA

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Topics: Thermal stratification , Engineering prototypes , Leakage , Fluid dynamics , Fluids , Safety , Simulation results , Test facilities

Safety Analysis of a Super Fast Reactor With Upward Flow Cooling in Two Pass at Supercritical Pressure

Takayoshi Kamata, Haipeng Li, Yoshiaki Oka, Yuki Ishiwatari

ICONE 2013; V002T05A013https://doi.org/10.1115/ICONE21-15587

Abstract

View Articletitled, Safety Analysis of a Super Fast Reactor With Upward Flow Cooling in Two Pass at Supercritical Pressure

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Topics: Cooling , Fast neutron reactors , Flow (Dynamics) , Pressure , Safety , Coolants , Accidents , Fuels , Transients (Dynamics) , Buoyancy

The Computer Measuring and Controlling System for Temperature Field of the Thermal-Shock Test at R1/R2 Test Section in ESPRESSO Loop

Fei Zhao, Chunliang Wu, Fengyang Shen, Chunxing Gu

ICONE 2013; V002T05A014https://doi.org/10.1115/ICONE21-15643

Abstract

View Articletitled, The Computer Measuring and Controlling System for Temperature Field of the Thermal-Shock Test at R1/R2 Test Section in ESPRESSO Loop

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Topics: Computers , Temperature , Thermal shock , Displacement , Shapes , Sodium

The Computer Measuring and Controlling System for the Plugging Meter of the Mobile Sodium Purification Device

Fei Zhao, Fengyang Shen, Chunliang Wu, Yunyan Liu, Yu Sun

ICONE 2013; V002T05A015https://doi.org/10.1115/ICONE21-15645

Abstract

View Articletitled, The Computer Measuring and Controlling System for the Plugging Meter of the Mobile Sodium Purification Device

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Topics: Computers , Sodium , Temperature , Control algorithms , Curve fitting , Data acquisition , Flow (Dynamics) , Oxygen

The AP1000^® PWR Project Moving Toward Completion in China

Grenville Harrop

ICONE 2013; V002T05A016https://doi.org/10.1115/ICONE21-15664

Abstract

View Articletitled, The AP1000<sup>®</sup> PWR Project Moving Toward Completion in China

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Topics: China , Pressurized water reactors , Construction , Nuclear power , Boilers , Design , Fuels , Modular construction , Nuclear power stations , Reactor vessels

Preliminary Development of System Analysis Code for Traveling-Wave Reactor

Chao Guo, Daogang Lu, Hao Huang

ICONE 2013; V002T05A017https://doi.org/10.1115/ICONE21-15737

Abstract

View Articletitled, Preliminary Development of System Analysis Code for Traveling-Wave Reactor

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Topics: Systems analysis , Traveling waves , Fuels , Uranium , Light water reactors , Nuclear reactors , Safety , Centrifugal pumps , China , Design

Thermal-Hydraulic Study of Wire-Wrapped Blanket Assembly of CEFR

Yang Liu, Hong Yu, Yizhe Liu

ICONE 2013; V002T05A018https://doi.org/10.1115/ICONE21-15739

Abstract

View Articletitled, Thermal-Hydraulic Study of Wire-Wrapped Blanket Assembly of CEFR

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Topics: Manufacturing , Wire , Fuels , Coolants , Cross-flow , Flow (Dynamics) , Pressure drop , Rods , Sodium , China

High Breeding Core of a Supercritical-Pressure Light Water Cooled Fast Reactor

Taishi Yoshida, Yoshiaki Oka

ICONE 2013; V002T05A019https://doi.org/10.1115/ICONE21-15753

Abstract

View Articletitled, High Breeding Core of a Supercritical-Pressure Light Water Cooled Fast Reactor

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Topics: Fast neutron reactors , Pressure , Water , Fuels , Coolants , Rods , Cooling , Breeder reactors , Collisions (Physics) , Cross section (Physics)

Discussion on the Application of Fire Probability Safety Assessment to Sodium Cooled Fast Reactor

Wei Song, Hongyi Yang, Chunming Zhang, Jiaxu Zuo

ICONE 2013; V002T05A020https://doi.org/10.1115/ICONE21-15780

Abstract

View Articletitled, Discussion on the Application of Fire Probability Safety Assessment to Sodium Cooled Fast Reactor

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Topics: Fire , Probability , Safety , Sodium fast reactors , Sodium , Fast neutron reactors , Probabilistic safety assessment , Risk , Chemical reactions , China

A Study and Development of Primary Circuit Simulation Code for China Experimental Fast Reactor

Jin Wang, Donghui Zhang, Wenjun Hu, Lixia Ren

ICONE 2013; V002T05A021https://doi.org/10.1115/ICONE21-15790

Abstract

View Articletitled, A Study and Development of Primary Circuit Simulation Code for China Experimental Fast Reactor

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Topics: China , Circuits , Fast neutron reactors , Simulation , Sodium , Cooling , Coolants , Economics , Electricity (Physics) , Flow (Dynamics)

The Measurement and Analysis of CEFR Sodium Void Reactivity Effect

Keyuan Zhou, Hong Yu, Yun Hu, Xiaoliang Chen, Zhi Gang, Shixi Wang, Zehua Li

ICONE 2013; V002T05A022https://doi.org/10.1115/ICONE21-15799

Abstract

View Articletitled, The Measurement and Analysis of CEFR Sodium Void Reactivity Effect

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Topics: Sodium , Accidents , China , Fast neutron reactors , Reliability , Sodium fast reactors

Conceptual Studies of Design Scheme for Steam Generator in FBR

Zhenxing Zhang, Huajin Yu, Zhiguang Wu, Lina Zhu

ICONE 2013; V002T05A023https://doi.org/10.1115/ICONE21-15835

Abstract

View Articletitled, Conceptual Studies of Design Scheme for Steam Generator in FBR

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Topics: Boilers , Design , Optimization , China , Economics , Fast neutron reactors , Heat , Heat transfer , Safety

Optimization Design for Air Heat Exchanger of Large Fast Reactor Based on Genetic Algorithm

Huajin Yu, Lina Zhu, Zhenxing Zhang, Ziyu Liao

ICONE 2013; V002T05A024https://doi.org/10.1115/ICONE21-15848

Abstract

View Articletitled, Optimization Design for Air Heat Exchanger of Large Fast Reactor Based on Genetic Algorithm

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Topics: Design , Fast neutron reactors , Genetic algorithms , Heat exchangers , Optimization , Drag (Fluid dynamics) , Shells , Heat

The Measurement of the High Temperature Sodium Pipe in CEFR

Huajin Yu, Long Tang, Min Qi, Yuanwu Ye

ICONE 2013; V002T05A025https://doi.org/10.1115/ICONE21-15853

Abstract

View Articletitled, The Measurement of the High Temperature Sodium Pipe in CEFR

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Topics: High temperature , Pipes , Sodium , Displacement measurement , Displacement , Fast neutron reactors , Accidents , China , Circuits , Cooling systems

The Impact of Different Carrier Salts on the Physical Characteristics of the MSFR

Maosong Cheng, Jinhui Cheng, Zhimin Dai, Kun Chen

ICONE 2013; V002T05A026https://doi.org/10.1115/ICONE21-15871

Abstract

View Articletitled, The Impact of Different Carrier Salts on the Physical Characteristics of the MSFR

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Topics: Conceptual design , Design , Fast neutron reactors , Fuels , Natural resources , Neutrons , Nuclear fuel cycle , Radioactive wastes , Safety , Temperature

Stability Analysis of the MSBR

Maosong Cheng, Zhimin Dai

ICONE 2013; V002T05A027https://doi.org/10.1115/ICONE21-15887

Abstract

View Articletitled, Stability Analysis of the MSBR

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Topics: Stability , Temperature , Conceptual design , Molten salt reactors , Breeder reactors , Design , Equilibrium (Physics) , Fluids , Fuels , Graphite

Seismic Analysis of Lead-Bismuth-Cooled Fast Reactor Vessel

Juan Ma, Mei Huang

ICONE 2013; V002T05A028https://doi.org/10.1115/ICONE21-15899

Abstract

View Articletitled, Seismic Analysis of Lead-Bismuth-Cooled Fast Reactor Vessel

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Topics: Fast neutron reactors , Fluid structure interaction , Seismic analysis , Vessels , Reactor vessels , Earthquakes , Bellows (Equipment) , Density , Earthquake resistant design , Finite element analysis

Numerical Simulation and Analysis of Temperature Fluctuation in Core Outlet Zone of China Experimental Fast Reactor

Huanjun Zhu, Yijun Xu

ICONE 2013; V002T05A029https://doi.org/10.1115/ICONE21-15967

Abstract

View Articletitled, Numerical Simulation and Analysis of Temperature Fluctuation in Core Outlet Zone of China Experimental Fast Reactor

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Topics: China , Computer simulation , Fast neutron reactors , Temperature , Simulation , Turbulence , Boundary-value problems , Computational fluid dynamics , Computer software , Coolants

Neutronics Design of a Small LBE Cooled Accelerator Driven System CIADS

Xinzhe Wang, Hong Yu, Jian Zhang, Shixi Wang, Yun Hu, Tianying Duan

ICONE 2013; V002T05A030https://doi.org/10.1115/ICONE21-15994

Abstract

View Articletitled, Neutronics Design of a Small LBE Cooled Accelerator Driven System CIADS

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Topics: Design

A Heat Pipe Cooled Modular Reactor Concept for Manned Lunar Base Application

Gu Hu, Shouzhi Zhao, Zhiyong Sun, Chengzhi Yao

ICONE 2013; V002T05A031https://doi.org/10.1115/ICONE21-16006

Abstract

View Articletitled, A Heat Pipe Cooled Modular Reactor Concept for Manned Lunar Base Application

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Topics: Heat pipes , Coolants , Failure , Fast neutron reactors , Lithium , Potassium , Power systems (Machinery) , Waste heat

General Design Study on CSR1000 Structure

Hong-liang Zhang, Heng Fan, Ying Luo, Xiang Li, Xiao Liu, Yu Zhou

ICONE 2013; V002T05A032https://doi.org/10.1115/ICONE21-16064

Abstract

View Articletitled, General Design Study on CSR1000 Structure

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Topics: Design , China , Flow (Dynamics) , Flow-induced vibrations , Sealing (Process) , Thermal stresses , Water

Structure and Erosion Characteristics of Underexpanded Inert-Gas Jets Impinging on a Single Cylinder Submerged in Liquid Sodium

Hideyuki Kudoh, Ken-ichiro Sugiyama, Tadashi Narabayashi, Hiroyuki Ohshima, Akikazu Kurihara

ICONE 2013; V002T05A033https://doi.org/10.1115/ICONE21-16068

Abstract

View Articletitled, Structure and Erosion Characteristics of Underexpanded Inert-Gas Jets Impinging on a Single Cylinder Submerged in Liquid Sodium

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Topics: Cylinders , Erosion , Jets , Sodium , Drops , Flow (Dynamics) , Visualization , Heat transfer , Steam , Boilers

Preliminary Study on Thermal-Load Fluctuation Test Using HTTR

Daisuke Tochio, Yosuke Shimazaki, Kazuhiko Iigaki, Shigeaki Nakagawa, Shoji Takada, Nariaki Sakaba, Kazuhiro Sawa

ICONE 2013; V002T05A034https://doi.org/10.1115/ICONE21-16082

Abstract

View Articletitled, Preliminary Study on Thermal-Load Fluctuation Test Using HTTR

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Topics: Stress , Dynamics (Mechanics) , Hydrogen production , Combined heat and power , Design , Hydrogen , Industrial plants , Scram , Steady state , Very high temperature reactors

A Safety Evaluation of HTTR Core Components Against 2011 Tohoku Earthquake

Kazuhiko Iigaki, Masato Ono, Yosuke Shimazaki, Daisuke Tochio, Atsushi Shimizu, Hiroyuki Inoi, Shoji Takada, Kazuhiro Sawa

ICONE 2013; V002T05A035https://doi.org/10.1115/ICONE21-16091

Abstract

View Articletitled, A Safety Evaluation of HTTR Core Components Against 2011 Tohoku Earthquake

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Topics: Earthquakes , Safety , Seismic analysis , Design , Graphite , Inspection , Magnification , Optical quality control , Seismic waves , Stress

Improvement of Temperature Evaluation Model of Biological Shielding Concrete for HTTR Test Simulating LOFC With VCS Inactive

Shoji Takada, Shunki Yanagi, Kazuhiko Iigaki, Masanori Shinohara, Daisuke Tochio, Yosuke Shimazaki, Masato Ono, Kazuhiro Sawa

ICONE 2013; V002T05A036https://doi.org/10.1115/ICONE21-16095

Abstract

View Articletitled, Improvement of Temperature Evaluation Model of Biological Shielding Concrete for HTTR Test Simulating LOFC With VCS Inactive

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Topics: Concretes , Temperature , Cooling , Heat transfer , Fins , Heat conduction , Natural convection , Thermal radiation , Very high temperature reactors , Water

A Study on the Influences of Reactivity Feedback Mechanisms in China Experimental Fast Reactor Unprotected Transients

Yuanyu Wu, Hong Yu, Lixia Ren, Wenjun Hu, Hongtao Qian

ICONE 2013; V002T05A037https://doi.org/10.1115/ICONE21-16114

Abstract

View Articletitled, A Study on the Influences of Reactivity Feedback Mechanisms in China Experimental Fast Reactor Unprotected Transients

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Topics: China , Fast neutron reactors , Feedback , Transients (Dynamics) , Accidents , Coolants , Flow (Dynamics) , Fuels , Temperature , Design

Investigation on Iodine Release Behavior During the Operation of High Temperature Engineering Test Reactor (HTTR)

Shohei Ueta, Hiroyuki Inoi, Yoshitaka Mizutani, Hirofumi Ohashi, Jin Iwatsuki, Nariaki Sakaba, Kazuhiro Sawa

ICONE 2013; V002T05A038https://doi.org/10.1115/ICONE21-16128

Abstract

View Articletitled, Investigation on Iodine Release Behavior During the Operation of High Temperature Engineering Test Reactor (HTTR)

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Topics: High temperature , Coolants , Isotopes , Testing , Circuits , Cooling , Fuels , Nuclear power , Nuclides , Radiation (Physics)

Transient Analysis of Passive Decay Heat Removal System for CEFR

H. Qian, Z. Li, L. Ren

ICONE 2013; V002T05A039https://doi.org/10.1115/ICONE21-16132

Abstract

View Articletitled, Transient Analysis of Passive Decay Heat Removal System for CEFR

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Topics: Heat , Transient analysis , Steady state , Accidents , Circuits , Cladding systems (Building) , Fast neutron reactors , Temperature , Thermal hydraulics , Transients (Dynamics)

Preliminary Research and Design in the Nuclear Island Systems of 1500MWt Standing-Wave Reactor

Tianying Duan, Peide Zhou, Bin Long, Yun Hu, Yizhe Liu, Chen Huang, Huajin Yu, Gang Sun, Yuanyuan Zhang, Chunli Yu, Weiwei Feng, Haojie Liu

ICONE 2013; V002T05A040https://doi.org/10.1115/ICONE21-16134

Abstract

View Articletitled, Preliminary Research and Design in the Nuclear Island Systems of 1500MWt Standing-Wave Reactor

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Topics: Design , Standing waves , Fuels , Uranium , Physics , Chain , Cladding systems (Building) , Fast neutron reactors , Nuclear fission , Sodium fast reactors

Study on Seismic Fragility of Air Heat Exchanger for CEFR

Zhiwei Fu, Donghui Zhang, Tianyi Zhang, Chunming Zhang, Jiaxu Zuo, Yan Chen, Wei Song, Zhe Wang

ICONE 2013; V002T05A041https://doi.org/10.1115/ICONE21-16138

Abstract

View Articletitled, Study on Seismic Fragility of Air Heat Exchanger for CEFR

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Topics: Failure , Heat exchangers , Uncertainty

The Analysis of Sedimentation Rate of Sodium Aerosol in a Hypothetical Accident of CEFR

Dajie Sun, Donghui Zhang, Lixia Ren

ICONE 2013; V002T05A042https://doi.org/10.1115/ICONE21-16140

Abstract

View Articletitled, The Analysis of Sedimentation Rate of Sodium Aerosol in a Hypothetical Accident of CEFR

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Topics: Accidents , Aerosols , Sedimentation , Sodium , Fire , Ventilation , Chemical properties , China , Fast neutron reactors , Gravity (Force)

The Design of a Small Annular Linear Induction EM Pump for the Transportation of Liquid Sodium in the SFR

Hee Reyoung Kim

ICONE 2013; V002T05A043https://doi.org/10.1115/ICONE21-16162

Abstract

View Articletitled, The Design of a Small Annular Linear Induction EM Pump for the Transportation of Liquid Sodium in the SFR

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Topics: Design , Electromagnetic induction , Pumps , Sodium , Sodium fast reactors , Transportation systems , Pressure , High temperature , Circuits , Coolants

The First Criticality Experiment of CEFR

Xiaoyan Yang, Hong Yu, Zhi Gang, Keyuan Zhou, Jinkun Zhao, Yiyu Chen, Yun Hu, Hechun Tian, Zehua Li

ICONE 2013; V002T05A044https://doi.org/10.1115/ICONE21-16187

Abstract

View Articletitled, The First Criticality Experiment of CEFR

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Topics: China , Fast neutron reactors , Fuels , Theoretical analysis

Neutronics Design Study on Ignition Zone of Travelling Wave Reactor

Jian Zhang, Hong Yu, Zhi Gang, Keyuan Zhou, Yun Hu, Tianying Duan

ICONE 2013; V002T05A045https://doi.org/10.1115/ICONE21-16194

Abstract

View Articletitled, Neutronics Design Study on Ignition Zone of Travelling Wave Reactor

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Topics: Design , Ignition , Traveling waves

Thermal Hydraulic Analysis of a SCWR Core Concept

Weizhong Zhang

ICONE 2013; V002T05A046https://doi.org/10.1115/ICONE21-16217

Abstract

View Articletitled, Thermal Hydraulic Analysis of a SCWR Core Concept

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Topics: Supercritical water reactors , Water , Coolants , Fuels , Rods , Temperature , Cladding systems (Building) , Conceptual design , Manufacturing , Pins (Engineering)

Experimental Study on the Sodium Spray Fire

Haiou Du, Chen Liu, Rongdong Wang, Wenjun Hu

ICONE 2013; V002T05A047https://doi.org/10.1115/ICONE21-16237

Abstract

View Articletitled, Experimental Study on the Sodium Spray Fire

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Topics: Fire , Sodium , Sprays , Combustion , Temperature , Pressure , Accidents , Data acquisition systems , Design , Instrumentation

A Neutronics Concept Design of Lead-Bismuth Cooled Accelerator-Driven System for Minor Actinide Transmutation

Xunzhao Li, Hongchun Wu, Liangzhi Cao, Youqi Zheng

ICONE 2013; V002T05A048https://doi.org/10.1115/ICONE21-16309

Abstract

View Articletitled, A Neutronics Concept Design of Lead-Bismuth Cooled Accelerator-Driven System for Minor Actinide Transmutation

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Topics: Design , Fuels , Proton beams , Protons , Spallation (Nuclear physics) , Light water reactors , Neutron sources , Neutrons , Thermal energy , Transuranium elements

Fracture Mechanic at Design Level for New Reactors

Claude Faidy

ICONE 2013; V002T05A049https://doi.org/10.1115/ICONE21-16377

Abstract

View Articletitled, Fracture Mechanic at Design Level for New Reactors

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Topics: Design , Fracture (Materials) , Accidents , Brittleness , Corrosion , Emergencies , Failure mechanisms , Fatigue , Leak-before-break , Phase transition temperature

Licensing Considerations of a Fluoride Salt Cooled High Temperature Test Reactor

Yao Xiao, Lin-wen Hu, Charles Forsberg, Suizheng Qiu, Guanghui Su

ICONE 2013; V002T05A050https://doi.org/10.1115/ICONE21-16383

Abstract

View Articletitled, Licensing Considerations of a Fluoride Salt Cooled High Temperature Test Reactor

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Topics: High temperature , Licensing , Coolants , Design , Temperature , China , Construction , Forced convection , Fuels , Physics

Measurement of Reaction Rate Distribution and Neutron Spectrum in China Experimental Fast Reactor

Xiaoliang Chen, Zhendong Fan, Xiaoxian Chen, Dingsheng Hu

ICONE 2013; V002T05A051https://doi.org/10.1115/ICONE21-16413

Abstract

View Articletitled, Measurement of Reaction Rate Distribution and Neutron Spectrum in China Experimental Fast Reactor

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Topics: China , Fast neutron reactors , Neutrons , Irradiation (Radiation exposure) , Gamma rays , Germanium , Nuclear fission , Physics

Investigation on the Compatibility of Fe-Ni Magnetic Alloy With High Temperature Sodium

Jin-quan Zhang, Pei-de Zhou, Yong-li Xu, Chun Xie, Xiao-gang Fu, Bin Long

ICONE 2013; V002T05A052https://doi.org/10.1115/ICONE21-16415

Abstract

View Articletitled, Investigation on the Compatibility of Fe-Ni Magnetic Alloy With High Temperature Sodium

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Topics: Corrosion , High temperature , Magnetic alloys , Sodium

Mechanism of Flow Drag Reduction on Non-Smooth Surface

Beibei Feng, Darong Chen, Jiadao Wang, Xingtuan Yang

ICONE 2013; V002T05A053https://doi.org/10.1115/ICONE21-16493

Abstract

View Articletitled, Mechanism of Flow Drag Reduction on Non-Smooth Surface

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Topics: Drag reduction , Flow (Dynamics) , Vortices , Air flow , Computer simulation , Form drag , Momentum , Pressure , Shear (Mechanics) , Shear stress

Status of the Combined Third and Fourth NGNP Fuel Irradiations in the Advanced Test Reactor

S. Blaine Grover, David A. Petti, Michael E. Davenport

ICONE 2013; V002T05A054https://doi.org/10.1115/ICONE21-16497

Abstract

View Articletitled, Status of the Combined Third and Fourth NGNP Fuel Irradiations in the Advanced Test Reactor

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Topics: Fuels , Irradiation (Radiation exposure) , Nuclear fission , Design , Particulate matter , High temperature , Monitoring systems , Nuclear power stations , Safety , Spent nuclear fuels

Preliminary Safety Analysis of CSR1000

Pan Wu, Junli Gou, Jianqiang Shan, Bo Zhang, Xiang Li

ICONE 2013; V002T05A055https://doi.org/10.1115/ICONE21-16502

Abstract

View Articletitled, Preliminary Safety Analysis of CSR1000

PDF

Topics: Safety , Accidents , Coolants , Supercritical water reactors , China , Cladding systems (Building) , Delays , Design , Flow (Dynamics) , Nuclear power

Neutronic Analysis of the HTTR Core Fueled With Plutonium and Minor Actinides

Chun-Yen Li, Rong-Jiun Sheu, Jinn-Jer Peir, Der-Sheng Chao, Jenq-Horng Liang

ICONE 2013; V002T05A056https://doi.org/10.1115/ICONE21-16507

Abstract

View Articletitled, Neutronic Analysis of the HTTR Core Fueled With Plutonium and Minor Actinides

PDF

Topics: Combustion , Design , Fuels , Graphite , Helium , High temperature , Light water reactors , Neutrons , Particulate matter , Safety

The Testing and Application of Continuous-Energy Neutron Cross Section Library HENDL-ADS/MC

Chong Chen, Jun Zou, Dezheng Xu, Qin Zeng, Minghuang Wang

ICONE 2013; V002T05A057https://doi.org/10.1115/ICONE21-16514

Abstract

View Articletitled, The Testing and Application of Continuous-Energy Neutron Cross Section Library HENDL-ADS/MC

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Topics: Neutrons , Testing , Reliability , Nuclear fission , Nuclides , Safety , Teams , Temperature

Coupled Neutronics/Thermal-Hydraulics Analysis of PT–SCWR With 54-Element Bundle Design

Jia Feng, Jianqiang Shan, Bo Zhang

ICONE 2013; V002T05A058https://doi.org/10.1115/ICONE21-16516

Abstract

View Articletitled, Coupled Neutronics/Thermal-Hydraulics Analysis of PT–SCWR With 54-Element Bundle Design

PDF

Topics: Design , Supercritical water reactors , Thermal hydraulics , Cladding systems (Building) , Temperature , Cycles , Water , Coolants , Fuels , Optimization

Probabilistic Distribution of Parameters Applied to PFM Analysis for Piping in China Experimental Fast Reactor

Min Qi, Yueying Wang, Jia Liu

ICONE 2013; V002T05A059https://doi.org/10.1115/ICONE21-16520

Abstract

View Articletitled, Probabilistic Distribution of Parameters Applied to PFM Analysis for Piping in China Experimental Fast Reactor

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Topics: China , Fast neutron reactors , Pipes , Fracture mechanics , Design for Manufacturing , Dimensions , Fittings , Pressure vessels , Probabilistic safety assessment , Probability

Thermal Hydraulic Analysis Code Development for DHRS of SFR

Xiaokun Wang, Donghui Zhang

ICONE 2013; V002T05A060https://doi.org/10.1115/ICONE21-16543

Abstract

View Articletitled, Thermal Hydraulic Analysis Code Development for DHRS of SFR

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Topics: Sodium fast reactors , Boundary-value problems , Heat , Heat exchangers , Temperature , Transients (Dynamics) , China , Drag (Fluid dynamics) , Fast neutron reactors , Flow (Dynamics)

Temperature Field Analysis for Freezing Sealing Structure of Sodium Gate Valve in China Experiment Fast Reactor (CEFR)

Lina Hu, Huajin Yu, Mingyu Lv

ICONE 2013; V002T05A061https://doi.org/10.1115/ICONE21-16544

Abstract

View Articletitled, Temperature Field Analysis for Freezing Sealing Structure of Sodium Gate Valve in China Experiment Fast Reactor (CEFR)

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Topics: China , Fast neutron reactors , Freezing , Gates (Closures) , Sealing (Process) , Sodium , Temperature , Valves , Computer software , Design

Preliminary Thermal-Hydraulic Analyses for Designing an Experimental Model of a Molten Salt Reactor Concept

Bogdán Yamaji, Attila Aszódi

ICONE 2013; V002T05A062https://doi.org/10.1115/ICONE21-16592

Abstract

View Articletitled, Preliminary Thermal-Hydraulic Analyses for Designing an Experimental Model of a Molten Salt Reactor Concept

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Topics: Design , Molten salt reactors , Computational fluid dynamics , Fast neutron reactors , Modeling , Circuits , Coolants , Cycles , Flow (Dynamics) , Flow measurement

The Investigation of Minor Losses in T-Pipe Flow

Dajie Sun, Donghui Zhang, Wenjun Hu, Lixia Ren

ICONE 2013; V002T05A063https://doi.org/10.1115/ICONE21-16610

Abstract

View Articletitled, The Investigation of Minor Losses in T-Pipe Flow

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Topics: Flow (Dynamics) , Pipes , Pressure drop , Pressure , Safety , Design , Fast neutron reactors , Fittings , Rods , Sodium

Numerical Investigations on Instabilities in Supercritical Water Flowing Through Heated Parallel Channels

Bharat Mangukiya, Manmohan Pandey

ICONE 2013; V002T05A064https://doi.org/10.1115/ICONE21-16628

Abstract

View Articletitled, Numerical Investigations on Instabilities in Supercritical Water Flowing Through Heated Parallel Channels

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Topics: Water , Temperature , Computer simulation , Heat flux , Pressure , Supercritical water reactors , Boundary-value problems , Coolants , Equations of state , Flow (Dynamics)

Study on Design of Scaled Down Test Facilities for Investigation of Instabilities in Supercritical Water Reactor

Daya Shankar, Dipankar N. Basu, Manmohan Pandey

ICONE 2013; V002T05A065https://doi.org/10.1115/ICONE21-16638

Abstract

View Articletitled, Study on Design of Scaled Down Test Facilities for Investigation of Instabilities in Supercritical Water Reactor

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Topics: Design , Supercritical water reactors , Test facilities , Fluids , Boiling water reactors , High pressure (Physics) , Kinematics , Modeling , Plant design , Stability

AFCR and EC6: The Two Sister Products

Frank Yee, Sermet Kuran, Mike Soulard, Zhenhua Zhang

ICONE 2013; V002T05A066https://doi.org/10.1115/ICONE21-16646

Abstract

View Articletitled, AFCR and EC6: The Two Sister Products

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Topics: China , Cycles , Design , Fuels , Fukushima nuclear disaster, Japan, 2011 , Uranium

Enhancement of Plant Availability by Outage Shortening in European Advanced Boiling Water Reactor (EU-ABWR)

Kazuhiro Kamei, Kazuyoshi Kataoka, Kazuto Imasaki, Noboru Saito

ICONE 2013; V002T05A067https://doi.org/10.1115/ICONE21-16681

Abstract

View Articletitled, Enhancement of Plant Availability by Outage Shortening in European Advanced Boiling Water Reactor (EU-ABWR)

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Topics: Boiling water reactors , Design , Safety , Sprays , Accidents , Aircraft , Computation , Computational fluid dynamics , Fluid dynamics , Inspection

Safety Performance of a Large Scale Sodium Cooled Fast Reactor in Unprotected Transient Overpower Scenarios

Yuanyu Wu, Hong Yu, Lixia Ren, Wenjun Hu

ICONE 2013; V002T05A068https://doi.org/10.1115/ICONE21-16704

Abstract

View Articletitled, Safety Performance of a Large Scale Sodium Cooled Fast Reactor in Unprotected Transient Overpower Scenarios

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Topics: Safety , Sodium fast reactors , Transients (Dynamics) , Design , China , Fast neutron reactors , Cladding systems (Building) , Fuels , Simulation , Sodium

CFD Investigation of Heat Transfer Deterioration in Supercritical Water Flowing Through Vertical Annular Channels

U. S. Tejaswini, Dipankar N. Basu, Manmohan Pandey

ICONE 2013; V002T05A069https://doi.org/10.1115/ICONE21-16720

Abstract

View Articletitled, CFD Investigation of Heat Transfer Deterioration in Supercritical Water Flowing Through Vertical Annular Channels

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Topics: Computational fluid dynamics , Heat transfer , Water , Flow (Dynamics) , Supercritical water reactors , Temperature , Annulus , Buoyancy , Computer simulation , Computer software

Experimental Modelling of a Molten Salt Reactor Concept

Bogdán Yamaji, Attila Aszódi

ICONE 2013; V002T05A070https://doi.org/10.1115/ICONE21-16783

Abstract

View Articletitled, Experimental Modelling of a Molten Salt Reactor Concept

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Topics: Circuits , Computational fluid dynamics , Coolants , Cycles , Design , Engineering simulation , Fast neutron reactors , Fluids , Fuels , Geometry

Wave Propagation in the Hot Duct of VHTR

Jim C. P. Liou, Richard R. Schultz

ICONE 2013; V002T05A071https://doi.org/10.1115/ICONE21-16807

Abstract

View Articletitled, Wave Propagation in the Hot Duct of VHTR

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Topics: Ducts , Very high temperature reactors , Wave propagation , Helium , Rupture , Pressure , Reactor vessels , Transients (Dynamics) , Algorithms , Boilers

Fast Reactor Design Using the Advanced Reactor Modeling Interface

Jesse Cheatham, Bao Truong, Nicholas Touran, Ryan Latta, Mark Reed, Robert Petroski

ICONE 2013; V002T05A072https://doi.org/10.1115/ICONE21-16815

Abstract

View Articletitled, Fast Reactor Design Using the Advanced Reactor Modeling Interface

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Topics: Design , Fast neutron reactors , Modeling , Transients (Dynamics) , Fuels , Simulation , Steady state , Teams , Engines , Equilibrium (Physics)

Feasibility Study of Utilizing TRISO Fuel in PWR Technology

Anwar Hussain, Ammar Khan

ICONE 2013; V002T05A073https://doi.org/10.1115/ICONE21-16862

Abstract

View Articletitled, Feasibility Study of Utilizing TRISO Fuel in PWR Technology

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Topics: Fuels , Heating , Pressurized water reactors

Overview on the Design Approach for the CVCS I & C of the EPR™ Nuclear Power Plant in Taishan

Antonio Ciriello, Daniela Kohler, Terry Morton, Thomas Lang

ICONE 2013; V002T05A074https://doi.org/10.1115/ICONE21-16870

Abstract

View Articletitled, Overview on the Design Approach for the CVCS I & C of the EPR™ Nuclear Power Plant in Taishan

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Topics: Design , Nuclear power stations , Collaboration , Control systems , Engineering design , Instrumentation , Safety

LOCA Break Spectrum Analysis of the Westinghouse Small Modular Reactor

Vefa N. Kucukboyaci, Jun Liao

ICONE 2013; V002T05A075https://doi.org/10.1115/ICONE21-16884

Abstract

View Articletitled, LOCA Break Spectrum Analysis of the Westinghouse Small Modular Reactor

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Topics: Emission spectroscopy , Small modular reactors , Spectroscopy , Safety , Design , Pressurized water reactors , Reactor vessels , Accidents , Boilers , Containment

Research of Features of U-Pu-Th Fuel Cycle and its Use for Burning Up of Minor Actinides in Supercritical Water-Cooled Reactor With Fast Neutron Spectrum

Alexander P. Glebov, Alexey V. Klushin, Yuriy D. Baranaev, Pavel L. Kirillov

ICONE 2013; V002T05A076https://doi.org/10.1115/ICONE21-16888

Abstract

View Articletitled, Research of Features of U-Pu-Th Fuel Cycle and its Use for Burning Up of Minor Actinides in Supercritical Water-Cooled Reactor With Fast Neutron Spectrum

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Topics: Combustion , Neutrons , Nuclear fuel cycle , Water , Fuels , Cycles , Coolants , Flow (Dynamics) , Isotopes , Pins (Engineering)

The European Utility Requirements (EUR): A Great Achievement and Still on its Way

Eric de Fraguier, Antoine Guelfi, Luc Vanhoenacker, Olivier Rousselot, Michel Béolet, Valérie Bellens

ICONE 2013; V002T05A077https://doi.org/10.1115/ICONE21-16914

Abstract

View Articletitled, The European Utility Requirements (EUR): A Great Achievement and Still on its Way

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Topics: Design , Disasters , Emissions , Feedback , Fukushima nuclear disaster, Japan, 2011 , Nuclear industry , Nuclear power , Power stations , Public utilities