Topics: Fuel rods , Pressurized water reactors , Thermomechanics , Three-dimensional modeling , Stress , Temperature , Accidents , Cladding systems (Building) , Displacement , Finite element analysis

A Novel Method for Solving Reactor Physics Diffusion and Transport Equation

Hu Wenjun, Cao Yonggang

ICONE 2017; V003T02A002doi:https://doi.org/10.1115/ICONE25-66045

Abstract

View Articletitled, A Novel Method for Solving Reactor Physics Diffusion and Transport Equation

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Topics: Diffusion (Physics) , Physics , Boundary-value problems , Computer software , Nuclear design , Numerical analysis

Adaptive Mesh Refinement for Neutron Transfer With Lattice Boltzmann Scheme

Yu Ma, Yahui Wang, Kuilong Song, Qian Sun

ICONE 2017; V003T02A003doi:https://doi.org/10.1115/ICONE25-66093

Abstract

View Articletitled, Adaptive Mesh Refinement for Neutron Transfer With Lattice Boltzmann Scheme

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Topics: Lattice Boltzmann methods , Neutrons , Boundary-value problems , Scalars , Simulation results

Refined Algorithm for Solving High-Order Harmonics of Multi Group Neutron Diffusion Equation

Gaoxin Zhou, Zhi Gang

ICONE 2017; V003T02A004doi:https://doi.org/10.1115/ICONE25-66098

Abstract

View Articletitled, Refined Algorithm for Solving High-Order Harmonics of Multi Group Neutron Diffusion Equation

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Topics: Algorithms , Diffusion (Physics) , Neutrons , Eigenvalues , Computational methods , Monitoring systems

Multi-Dimensional Shield Performance Analysis Through an Even Parity Based “Contributon” Transport Concept

Mostafa Yousefi, A. Zolfaghari, A. Minuchehr, M. R. Abbassi

ICONE 2017; V003T02A005doi:https://doi.org/10.1115/ICONE25-66124

Abstract

View Articletitled, Multi-Dimensional Shield Performance Analysis Through an Even Parity Based “Contributon” Transport Concept

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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

Takayuki Ozawa

ICONE 2017; V003T02A006doi:https://doi.org/10.1115/ICONE25-66129

Abstract

View Articletitled, Analysis of Fast Reactor Fuel Irradiation Behavior in the MA Recycle System

PDF

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

Xuming Wang, Cenxi Yuan, Chen Ye

ICONE 2017; V003T02A007doi:https://doi.org/10.1115/ICONE25-66204

Abstract

View Articletitled, Performances Analyses of Crud of EPR Fuel Assembly

PDF

Topics: Fuels , Manufacturing , Risk assessment , Boron , Pressurized water reactors , Risk , Cladding systems (Building) , Corrosion , Electricity (Physics) , European pressurized reactors

Research on Detailed Depletion Chain Solving Algorithm With the NUIT Code

Jian Li, Ding She, Lei Shi

ICONE 2017; V003T02A008doi:https://doi.org/10.1115/ICONE25-66238

Abstract

View Articletitled, Research on Detailed Depletion Chain Solving Algorithm With the NUIT Code

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Topics: Algorithms , Chain , Nuclides , Approximation , Polynomial approximation

A New Numerical Method for Fuel Temperature Calculation

Jin Xin, Xiaohan Liu, Xiaoyan Wei

ICONE 2017; V003T02A009doi:https://doi.org/10.1115/ICONE25-66248

Abstract

View Articletitled, A New Numerical Method for Fuel Temperature Calculation

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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

Yingming Song, Qingyu Gao, Ke Wang, Yaping Guo, Lu Zhang, Yongwei Yang

ICONE 2017; V003T02A010doi:https://doi.org/10.1115/ICONE25-66314

Abstract

View Articletitled, Simulation on Neutron Space-Time Kinetics for Accelerator Driven Sub-Critical System

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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

Zheng Zheng, Hui Li, Mengqi Wang

ICONE 2017; V003T02A011doi:https://doi.org/10.1115/ICONE25-66401

Abstract

View Articletitled, Application of a 3D Discrete Ordinates-Monte Carlo Coupling Method on CAP1400 Cavity Streaming Calculation

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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

Muhammad Qasim Awan, Liangzhi Cao, Hongchun Wu

ICONE 2017; V003T02A012doi:https://doi.org/10.1115/ICONE25-66444

Abstract

View Articletitled, Burnable Poisons Alternative Configurations in AT-FCM PWR Fuel Assembly

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Topics: Fuels , Manufacturing , Pressurized water reactors , Boron , Cycles , Nuclear reactors , Safety , Accidents , High temperature , Ceramics

Effects of Neutron Irradiation on the Mechanical and Electromagnetic Properties of Reactor Pressure Vessel Steels

Li Chengliang, Shu Guogang, Chen Jun, Liu Yi, Liu Wei, Hu Yichuan, Duan Yuangang, Liu Feihua

ICONE 2017; V003T02A013doi:https://doi.org/10.1115/ICONE25-66464

Abstract

View Articletitled, Effects of Neutron Irradiation on the Mechanical and Electromagnetic Properties of Reactor Pressure Vessel Steels

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Topics: Irradiation (Radiation exposure) , Neutrons , Reactor vessels , Steel , Damage , Electrical resistivity , Ductility , Failure mechanisms , Fracture toughness , Magnetization

Newly Developed Coupling Scheme in RMC With Internal Thermal Feedback and OTF Doppler-Broadening Method

Ouwen Yexin, Shanfang Huang, Kan Wang

ICONE 2017; V003T02A014doi:https://doi.org/10.1115/ICONE25-66519

Abstract

View Articletitled, Newly Developed Coupling Scheme in RMC With Internal Thermal Feedback and OTF Doppler-Broadening Method

PDF

Topics: Feedback , Nuclear reactors , Steady state , Fuels , Hydraulics , Manufacturing , Physics , Pressurized water reactors , Simulation , Simulation analysis

Development and Verification of Multi-Group Cross Section Process Code TXMAT for Fast Reactor RBEC-M Analysis

Ruomeng Qiu, Xubo Ma, Qian Xu, Jiayi Liu, Yixue Chen

ICONE 2017; V003T02A015doi:https://doi.org/10.1115/ICONE25-66550

Abstract

View Articletitled, Development and Verification of Multi-Group Cross Section Process Code TXMAT for Fast Reactor RBEC-M Analysis

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Topics: Fast neutron reactors , Cross section (Physics) , Absorption , Computer programming , Diffusion (Physics) , Errors , Isotopes , Neutrons , Nuclear fission , S-matrix theory

New Exploration on TMSR: Redesign of the TMSR Lattice

Jinkun Zhao, Shengyi Si, Qichang Chen, Hua Bei

ICONE 2017; V003T02A016doi:https://doi.org/10.1115/ICONE25-66564

Abstract

View Articletitled, New Exploration on TMSR: Redesign of the TMSR Lattice

PDF

Topics: Breeder reactors , Ceramics , Cladding systems (Building) , Coolants , Corrosion , Design , Fast neutron reactors , Flow (Dynamics) , Fluids , Fuels

Numerical Comparison and Analysis of Nuclear Core Design Code System SCAP and MPACT

Weiyan Yang, Chuntao Tang, Hongbo Zhang, Bo Yang

ICONE 2017; V003T02A017doi:https://doi.org/10.1115/ICONE25-66567

Abstract

View Articletitled, Numerical Comparison and Analysis of Nuclear Core Design Code System SCAP and MPACT

PDF

Topics: Design , Nuclear power stations , Boron , Cycles , Electrical measurement , Nuclear engineering , Simulation

Development and Verification of the PWR Lattice Code PANDA

Hongbo Zhang, Chuntao Tang, Weiyan Yang, Guangwen Bi, Bo Yang

ICONE 2017; V003T02A018doi:https://doi.org/10.1115/ICONE25-66573

Abstract

View Articletitled, Development and Verification of the PWR Lattice Code PANDA

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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

Jiwei Li, Yang Ding, Wentao Liu, Guangwen Bi, Ruirui Zhao, Qin Zhou

ICONE 2017; V003T02A019doi:https://doi.org/10.1115/ICONE25-66585

Abstract

View Articletitled, Out-of-Pile Properties Investigation of UO2-BeO Fuel Pellet

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Topics: Fuels , Thermal conductivity , Elastic moduli , Thermal expansion , Uranium , Composite materials , Nuclear power stations , Sintering

Test Reactor Irradiation Fuel Assembly Development in China

Jie Ding, Yixiong Zheng, Yang Ding, Song Liu, Libing Zhu, Jiazheng Liu

ICONE 2017; V003T02A020doi:https://doi.org/10.1115/ICONE25-66617

Abstract

View Articletitled, Test Reactor Irradiation Fuel Assembly Development in China

PDF

Topics: China , Fuels , Irradiation (Radiation exposure) , Manufacturing , Zirconium alloys , Alloys , Corrosion , Creep , Finishes , Fuel rods

Research on Estimating Methods and Application of Fuel Rods Defect

Huaibin Li, Yaru Fu, Lanfang Mao, Qiliang Mei

ICONE 2017; V003T02A021doi:https://doi.org/10.1115/ICONE25-66622

Abstract

View Articletitled, Research on Estimating Methods and Application of Fuel Rods Defect

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Topics: Fuel rods , Fuel management , Nuclear fission , Nuclear power stations , Nuclear reactor coolants , Economics , Evaluation methods , Nuclides , Radiation (Physics) , Safety

Development and Application of Cobalt Adjuster Rod for ⁶⁰Co Medical Radioactive Sources Production in CANDU-6 Reactor

Jie Ding, Yu Dang, Libing Zhu, Chuntao Tang, Hui Li, Huimin Qin

ICONE 2017; V003T02A022doi:https://doi.org/10.1115/ICONE25-66623

Abstract

View Articletitled, Development and Application of Cobalt Adjuster Rod for 60Co Medical Radioactive Sources Production in CANDU-6 Reactor

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Topics: Biomedicine , Cobalt , Design , Safety , Manufacturing , Nuclear design

An Innovative Spherical Fuel Element to Inhibit the Infiltration of Liquid Fluoride Salt in Molten Salt Reactor

Yajuan Zhong, Jun Lin, Liujun Xu, Haitao Jiang, Zhiyong Zhu

ICONE 2017; V003T02A023doi:https://doi.org/10.1115/ICONE25-66639

Abstract

View Articletitled, An Innovative Spherical Fuel Element to Inhibit the Infiltration of Liquid Fluoride Salt in Molten Salt Reactor

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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; V003T02A024doi:https://doi.org/10.1115/ICONE25-66659

Abstract

View Articletitled, Research and Engineering Application of Repaired Fuel Assembly Reusing Technique

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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; V003T02A025doi:https://doi.org/10.1115/ICONE25-66700

Abstract

View Articletitled, CAP1400 Fuel Assembly Development and PWR Fuel Assembly Technology Progress in China

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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

Junqiang Lu, Lei Chen, Congzhang Qiu, Weiyan Yang, Feifei Zhang, Ruifang Yang

ICONE 2017; V003T02A026doi:https://doi.org/10.1115/ICONE25-66747

Abstract

View Articletitled, Preparation and Properties Investigation of Neutron Absorber Material Mo-Tb-Dy and Y-Tb-Dy Alloys

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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

Yangbin Deng, Bowen Qiu, Yingwei Wu, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G. H. Su

ICONE 2017; V003T02A027doi:https://doi.org/10.1115/ICONE25-66774

Abstract

View Articletitled, Simulation on Pellet-Cladding Mechanical Interaction (PCMI) of Accident Tolerant Fuel (ATF) With Coated Cladding

PDF

Topics: Accidents , Cladding systems (Building) , Fuels , Simulation , Coatings , Zirconium , Alloys , Fuel rods , Pressure , Stress

A New Method to Evaluate the Correlation Coefficients Between Nuclides in Uncertainty and Sensitivity Analysis

Xu Jia Yi, Ma Xu Bo, Shen Jing Wen, Liu Jia Yi, Chen Yi Xue

ICONE 2017; V003T02A028doi:https://doi.org/10.1115/ICONE25-66777

Abstract

View Articletitled, A New Method to Evaluate the Correlation Coefficients Between Nuclides in Uncertainty and Sensitivity Analysis

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Topics: Nuclides , Sensitivity analysis , Uncertainty , Isotopes , Cross section (Physics) , Density , Pressurized water reactors , Cycles , Fast neutron reactors , Nuclear engineering

Methodology to Construct Burnup Profile of Fuel Pebbles in PBR

Yushi Tang, Liguo Zhang, Qiuju Guo, Jianzhu Cao, Jiejuan Tong

ICONE 2017; V003T02A029doi:https://doi.org/10.1115/ICONE25-66795

Abstract

View Articletitled, Methodology to Construct Burnup Profile of Fuel Pebbles in PBR

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Topics: Fuels , Discrete element methods , Flow (Dynamics) , Economics , Safety , Cycles , Gas cooled reactors , Irradiation (Radiation exposure) , Kinematics , Simulation

Resonance Self-Shielding Treatment for Fully Ceramic Micro-Encapsulated Fuels With the Embedded Self-Shielding Method

Jikui Li, Liangzhi Cao, Tiejun Zu, HongChun Wu, Qingming He

ICONE 2017; V003T02A030doi:https://doi.org/10.1115/ICONE25-66810

Abstract

View Articletitled, Resonance Self-Shielding Treatment for Fully Ceramic Micro-Encapsulated Fuels With the Embedded Self-Shielding Method

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Topics: Ceramics , Fuels , Resonance , Computational methods , Cross section (Physics) , Modeling , Particulate matter

Crucial Factors Analysis of 5×5 Grid Flow-Induced Vibration Test

C. Z. Zhang, J. Ding, Y. X. Zheng, F. J. Gan, S. J. Gong, Y. Mei

ICONE 2017; V003T02A031doi:https://doi.org/10.1115/ICONE25-66812

Abstract

View Articletitled, Crucial Factors Analysis of 5×5 Grid Flow-Induced Vibration Test

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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

Weiping Lan, Dachao Lin, Zulong Hao, Fenglei Niu

ICONE 2017; V003T02A032doi:https://doi.org/10.1115/ICONE25-66814

Abstract

View Articletitled, Stress Analysis of Three-Layer SiC Cladding for PWRs

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Topics: Cladding systems (Building) , Pressurized water reactors , Stress analysis (Engineering) , Fuels , Composite materials , Finite element analysis , Stress concentration , Temperature distribution , Coating processes , Coatings

Small Punch Test on Mechanical Properties of Molybdenum Single Crystal Weld

Yan Ma, Jianju Wang, Jinyun Lei

ICONE 2017; V003T02A033doi:https://doi.org/10.1115/ICONE25-66824

Abstract

View Articletitled, Small Punch Test on Mechanical Properties of Molybdenum Single Crystal Weld

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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

Jozef Molnar, Marek Pecka, Jaroslav Kment

ICONE 2017; V003T02A034doi:https://doi.org/10.1115/ICONE25-66867

Abstract

View Articletitled, SCORPIO-VVER: Two Decades of Experience and Enhancements in Reactor Core Monitoring and Surveillance in Central Europe

PDF

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

Xinpeng Li, Sheng Fang, Hong Li

ICONE 2017; V003T02A035doi:https://doi.org/10.1115/ICONE25-66923

Abstract

View Articletitled, A Resolution Enhancing Algorithm for Gamma-Ray Spectrum Based on Blind Deconvolution and Lp-Norm Sparsity Constraint

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Topics: Algorithms , Gamma rays , Resolution (Optics) , Emission spectroscopy , Oscillations , Spectroscopy , Computer simulation

The Verification of SONG Library

Hua Bei, Jinkun Zhao, Qichang Chen, Shengyi Si

ICONE 2017; V003T02A036doi:https://doi.org/10.1115/ICONE25-66946

Abstract

View Articletitled, The Verification of SONG Library

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Topics: Absorption , Chemical kinetics , Cladding systems (Building) , Electromagnetic scattering , Fuels , Isotopes , Molten salt reactors , Nuclear fission , Pressurized water reactors , Radiation scattering

Microstructure and Properties of New Zirconium Alloys for CAP1400 Fuel Assembly

Qifeng Zeng, Libing Zhu, Gaihuan Yuan, Lian Wang, Guocheng Sun, Junqiang Lu

ICONE 2017; V003T02A037doi:https://doi.org/10.1115/ICONE25-66951

Abstract

View Articletitled, Microstructure and Properties of New Zirconium Alloys for CAP1400 Fuel Assembly

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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

Liutao Chen, Jun Tan, Changyuan Gao, Dungu Wen, Hong Zou, Yang Xu, Xu Wang

ICONE 2017; V003T02A038doi:https://doi.org/10.1115/ICONE25-67035

Abstract

View Articletitled, Effects of Annealing on the Corrosion Property of CZ1 Alloy

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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; V003T02A039doi:https://doi.org/10.1115/ICONE25-67054

Abstract

View Articletitled, Annealing Temperature Effect on Creep Property of CZ Alloy for PWR Modern Fuel Claddings

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Topics: Alloys , Annealing , Creep , Fuels , Pressurized water reactors , Temperature , Zirconium alloys , Stress , China , Cladding systems (Building)

Modeling and Thermal Calculation of Fuel Rod With SiC_f/SiC Cladding for LWRs

Shang Xinyuan, Zhang Shaoyang, Zhang Aimin

ICONE 2017; V003T02A040doi:https://doi.org/10.1115/ICONE25-67078

Abstract

View Articletitled, Modeling and Thermal Calculation of Fuel Rod With SiCf/SiC Cladding for LWRs

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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

Zhou Qin, Li Jiwei, Dang Yu, Ding Yang

ICONE 2017; V003T02A041doi:https://doi.org/10.1115/ICONE25-67112

Abstract

View Articletitled, Research on Nickel-Plated Hydrogen-Absorption Device in Fuel Rod and Performance Testing

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Topics: Absorption , Fuel rods , Hydrogen , Nickel plating , Testing performance , Cladding systems (Building) , Design , Pressure , Zirconium , Alloys

Stability of SPPs in Zirconium Alloy CZ2 Under Self-Ion Irradiation

Xu Wang, Jun Tan, Liutao Chen, Hong Zou, Dungu Wen, Yang Xu, Changyuan Gao, Yongjun Deng, Yuemin Zhou, Lumin Wang

ICONE 2017; V003T02A042doi:https://doi.org/10.1115/ICONE25-67128

Abstract

View Articletitled, Stability of SPPs in Zirconium Alloy CZ2 Under Self-Ion Irradiation

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Topics: Irradiation (Radiation exposure) , Stability , Zirconium alloys , Zirconium , Crystal structure , Temperature , Damage , Heat treating (Metalworking) , Particulate matter , Radiation effects

Modeling of Fuel Rod Behavior and Recent Advances of the JASMINE Code

Xiaoyan Wei, Xin Jin, Yongjun Deng, Guoliang Zhang, Xiangang Fu

ICONE 2017; V003T02A043doi:https://doi.org/10.1115/ICONE25-67144

Abstract

View Articletitled, Modeling of Fuel Rod Behavior and Recent Advances of the JASMINE Code

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Topics: Fuel rods , Modeling , China , Computer software , Nuclear power , Nuclear reactors

Development and Preliminary Verification of the 3D Core Neutronic Code: RCAD

Xiaosong Chen, Xin Xiong, Lianghui Peng, Zhi Gang, Zhihong Liu, Hong Xu

ICONE 2017; V003T02A044doi:https://doi.org/10.1115/ICONE25-67159

Abstract

View Articletitled, Development and Preliminary Verification of the 3D Core Neutronic Code: RCAD

PDF

Topics: Boundary-value problems , Design , Diffusion (Physics) , Errors , Light water reactors , Manufacturing , Pressurized water reactors

Calculation of the Macroscopic Group Constant of Pebble Bed Fluoride Salt Cooled High Temperature Reactor Based on the Collision Probability Method

Dida Zhang, Guobin Jia, Long He, Jiajie Shen, Zhichao Zhan, Hailing Wang, Wei Guo

ICONE 2017; V003T02A045doi:https://doi.org/10.1115/ICONE25-67194

Abstract

View Articletitled, Calculation of the Macroscopic Group Constant of Pebble Bed Fluoride Salt Cooled High Temperature Reactor Based on the Collision Probability Method

PDF

Topics: Collisions (Physics) , High temperature , Probability , Fuels , Generation IV reactors , Neutron flux

Microstructures and Properties of 304L Steel CAP1400 Fuel Bottom Nozzles Prepared by Additive Manufacturing Technology

Li Zongshu, Liu Wentao, Yang Songtao, Hao Ruotong

ICONE 2017; V003T02A046doi:https://doi.org/10.1115/ICONE25-67213

Abstract

View Articletitled, Microstructures and Properties of 304L Steel CAP1400 Fuel Bottom Nozzles Prepared by Additive Manufacturing Technology

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Topics: Additive manufacturing , Fuels , Nozzles , Steel , Manufacturing , Lasers , Fracture (Materials) , Fracture (Process) , Ferrites (Magnetic materials) , Mechanical properties

Influence of Oxygen Concentration on the Initiation of Dissolution Corrosion on 316L Austenitic Stainless Steel at 450°C

Oksana Klok, Konstantina Lambrinou, Serguei Gavrilov, Iris De Graeve

ICONE 2017; V003T02A047doi:https://doi.org/10.1115/ICONE25-67228

Abstract

View Articletitled, Influence of Oxygen Concentration on the Initiation of Dissolution Corrosion on 316L Austenitic Stainless Steel at 450°C

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Topics: Corrosion , Oxygen , Stainless steel , Oxidation , Scanning electron microscopy , Steel , X-ray spectroscopy

Microstructure and Properties Analysis of Inner Cladding Tube and End Plug Girth Weld of Annular Fuel Element

Ji Pengbo, Lu Hanghang, Wang Zhaosong, Zhang Zhoufeng, Liu Bin

ICONE 2017; V003T02A048doi:https://doi.org/10.1115/ICONE25-67243

Abstract

View Articletitled, Microstructure and Properties Analysis of Inner Cladding Tube and End Plug Girth Weld of Annular Fuel Element

PDF

Topics: Cladding systems (Building) , Fuels , Welding , Fracture (Materials) , Fracture (Process) , Microhardness , Heat , Pressurized water reactors , Tensile strength , Welded joints

A Comparative Study of 10 Different Methods on Numerical Solving of Point Reactor Neutron Kinetics Equations

Yining Zhang, Haochun Zhang, Yang Su, Guangbo Zhao

ICONE 2017; V003T02A049doi:https://doi.org/10.1115/ICONE25-67275

Abstract

View Articletitled, A Comparative Study of 10 Different Methods on Numerical Solving of Point Reactor Neutron Kinetics Equations

PDF

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

Pan Qingquan, Lu Haoliang, Li Dongsheng, Wang Kan

ICONE 2017; V003T02A050doi:https://doi.org/10.1115/ICONE25-67309

Abstract

View Articletitled, The Rigorous SP3 Theory and Study on its Numerical Verification

PDF

Topics: Approximation , Boundary-value problems , Leakage , Scalars

Code Development for the Neutronics/Thermal-Hydraulics Coupling Transient Analysis of Molten Salt Reactors

Tianliang Hu, Liangzhi Cao, Hongchun Wu, Kun Zhuang

ICONE 2017; V003T02A051doi:https://doi.org/10.1115/ICONE25-67316

Abstract

View Articletitled, Code Development for the Neutronics/Thermal-Hydraulics Coupling Transient Analysis of Molten Salt Reactors

PDF

Topics: Molten salt reactors , Thermal hydraulics , Transient analysis , Simulation , Transients (Dynamics) , Dynamics (Mechanics) , Cross section (Physics) , Flow (Dynamics) , Modeling , Slug flows

Investigation Into the Influence of Fuel Rods on the Anti-Seismic Mechanical Characteristics of Fuel Assembly Spacer Grid by FEM Method

Jingya Sun, Yu Dang, Song Liu, Jiazheng Liu, Libing Zhu

ICONE 2017; V003T02A052doi:https://doi.org/10.1115/ICONE25-67362

Abstract

View Articletitled, Investigation Into the Influence of Fuel Rods on the Anti-Seismic Mechanical Characteristics of Fuel Assembly Spacer Grid by FEM Method

PDF

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

Qiang Zhao, Zheng Zhang, Yang Li, Xiaoping Ouyang

ICONE 2017; V003T02A053doi:https://doi.org/10.1115/ICONE25-67365

Abstract

View Articletitled, Diffusion of Fission Gas in Uranium Dioxide: A First-Principles Study

PDF

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

Peng Dan, Wu Xiaobo, Lu Jin, Hao Qian, Hong Jingyan, Li Yiguo

ICONE 2017; V003T02A054doi:https://doi.org/10.1115/ICONE25-67384

Abstract

View Articletitled, Physics Design of Epi-Thermal Neutron Beam for BNCT Based on C-MNSR

PDF

Topics: Design , Neutron beams , Physics , Fuels , Neutrons , Cancer , Uranium , Boron , Contamination , Density

Simulation of the Delayed Hydride Cracking Velocity for Zirconium Alloy Materials Considering Irradiation Effects

Jingyu Zhang, Bingzhong Wang, Jiacheng Zhu, Shurong Ding, Liang Chen, Wenjie Li, Hua Pang

ICONE 2017; V003T02A055doi:https://doi.org/10.1115/ICONE25-67410

Abstract

View Articletitled, Simulation of the Delayed Hydride Cracking Velocity for Zirconium Alloy Materials Considering Irradiation Effects

PDF

Topics: Cracking (Materials) , Irradiation (Radiation exposure) , Simulation , Zirconium alloys , Embrittlement , Hardening , Traction , Anisotropy , Boundary-value problems , Computer simulation

Composite Versus Dispersed Accident Tolerant Nuclear Fuels

Jayangani Ranasinghe, Barbara Szpunar, Ericmoore Jossou, Linu Malakkal, Jerzy A. Szpunar

ICONE 2017; V003T02A056doi:https://doi.org/10.1115/ICONE25-67478

Abstract

View Articletitled, Composite Versus Dispersed Accident Tolerant Nuclear Fuels

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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

Feng Yan, Yunmei Zhao, Shurong Ding

ICONE 2017; V003T02A057doi:https://doi.org/10.1115/ICONE25-67531

Abstract

View Articletitled, Effect of Fuel Meat Thickness on the Non-Uniform Irradiation-Induced Thermo-Mechanical Behavior in Monolithic UMo/Al Fuel Plates

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Topics: Fuels , Irradiation (Radiation exposure) , Plates (structures) , Thermomechanics , Stress , Algorithms , Constitutive equations , Deformation , Density , Design

The Sensitivity Simulation of Different Geometric Pretreatment in Method of Characteristics

Tian XiaoRui, Zhou Tao, Li Zichao, Yu Tao

ICONE 2017; V003T02A058doi:https://doi.org/10.1115/ICONE25-67565

Abstract

View Articletitled, The Sensitivity Simulation of Different Geometric Pretreatment in Method of Characteristics

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Topics: Simulation , Simulation results , Physics , Storage

A Research Reactor Core Design for Advance Neutron Source

Zeyun Wu

ICONE 2017; V003T02A059doi:https://doi.org/10.1115/ICONE25-67573

Abstract

View Articletitled, A Research Reactor Core Design for Advance Neutron Source

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Topics: Design , Neutron sources , Heat flux , Brightness (Photometry) , Cycles , Fuels , Neutrons , Thermal energy

Physical Design on PMNSR With LEU Core

Wu Xiaobo, Peng Dan, Hong Jingyan, Lu Jin, Hao Qian

ICONE 2017; V003T02A060doi:https://doi.org/10.1115/ICONE25-67580

Abstract

View Articletitled, Physical Design on PMNSR With LEU Core

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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

Pan Qingquan, Lu Haoliang, Li Dongsheng, Wang Kan

ICONE 2017; V003T02A061doi:https://doi.org/10.1115/ICONE25-67597

Abstract

View Articletitled, Study on Semi-Analytical Nodal Method for Solving SP3 Equation

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Topics: Algebra , Diffusion (Physics) , Neutrons , Physics , Polynomials

The Effect of Minor Actinide Transmutation on Temperature Coefficient in PWR

Wenxin Zhang, Haoyang Yu, Bin Liu, Jin Cai, Shuangshuang Cui

ICONE 2017; V003T02A062doi:https://doi.org/10.1115/ICONE25-67649

Abstract

View Articletitled, The Effect of Minor Actinide Transmutation on Temperature Coefficient in PWR

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Topics: Pressurized water reactors , Temperature , Nuclides , Neutrons , Spent nuclear fuels , Half-life , Design , Irradiation (Radiation exposure) , Nuclear fission , Nuclear reactors

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; V003T02A063doi:https://doi.org/10.1115/ICONE25-67727

Abstract

View Articletitled, Verifying Calculation of the Parameters of AP1000 Core Design Based on MCNP Model

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Topics: Design , Nuclear power stations , Safety

Molecular Dynamics Simulation of the Sputtering of Graphite due to Bombardment With Deuterium and Tritium in Fusion Environment

Qiang Zhao, Yang Li, Zheng Zhang, Xiaoping Ouyang

ICONE 2017; V003T02A064doi:https://doi.org/10.1115/ICONE25-67781

Abstract

View Articletitled, Molecular Dynamics Simulation of the Sputtering of Graphite due to Bombardment With Deuterium and Tritium in Fusion Environment

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Topics: Graphite , Molecular dynamics simulation , Sputtering (Irradiation) , Temperature , Hydrogen , Carbon , Isotopes , Molecular dynamics methods

The Effect of MA Transmutation in the PWR on Fuel Cycle

Haoyang Yu, Bin Liu, Wenxin Zhang, Jin Cai

ICONE 2017; V003T02A065doi:https://doi.org/10.1115/ICONE25-67787

Abstract

View Articletitled, The Effect of MA Transmutation in the PWR on Fuel Cycle

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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

Marcel Strätz, Jörg Starflinger, Rainer Mertz, Michael Seewald, Sebastian Schuster, Dieter Brillert

ICONE 2017; V003T13A001doi:https://doi.org/10.1115/ICONE25-66084

Abstract

View Articletitled, Cycle Calculations of a Small-Scale Heat Removal System With Supercritical CO2 As Working Fluid

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Topics: Cycles , Fluids , Heat , Supercritical carbon dioxide , Accidents , Brayton cycle , Design , Electricity (Physics) , Heat sinks , Glass

The Comparison Research About Two Reliability Management Methods in AP1000 Design

Zhixin Xu, Chengzhang Wang, Jingjing Liu

ICONE 2017; V003T13A002doi:https://doi.org/10.1115/ICONE25-66089

Abstract

View Articletitled, The Comparison Research About Two Reliability Management Methods in AP1000 Design

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Topics: Design , Reliability , Nuclear power stations , Energy generation

Development of NPP Collaborative Design Management Platform

Shen Jun, Li Xiaoyan, Wang Yong

ICONE 2017; V003T13A003doi:https://doi.org/10.1115/ICONE25-66105

Abstract

View Articletitled, Development of NPP Collaborative Design Management Platform

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Topics: Design , Nuclear power stations , Construction , Nuclear design , Optimization

Study on TlBr Radioactive Detector

He Li-xia, Hao Xiao-yong, He Gao-kui

ICONE 2017; V003T13A004doi:https://doi.org/10.1115/ICONE25-66120

Abstract

View Articletitled, Study on TlBr Radioactive Detector

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Topics: Sensors , Resolution (Optics) , Atomic number , Density , Energy (Physics) , Energy gap , Engineering prototypes , Gamma rays , Inspection , Ionization energy

Design and Implementation of Visual Design Datacenter for Nuclear Power Plant

Lu Hui, Liu Zhong, Niu Bo, Zhang Lin, Rong Hui, Hu Chunping, Liu Yu

ICONE 2017; V003T13A005doi:https://doi.org/10.1115/ICONE25-66171

Abstract

View Articletitled, Design and Implementation of Visual Design Datacenter for Nuclear Power Plant

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Topics: Design , Nuclear power stations , Computer software , Computer-aided design , Data fusion

Application of the Burnable Poison in the Design of Space Nuclear Reactor

Wang SanBing, Xie Qilin, He ChaoHui

ICONE 2017; V003T13A006doi:https://doi.org/10.1115/ICONE25-66393

Abstract

View Articletitled, Application of the Burnable Poison in the Design of Space Nuclear Reactor

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Topics: Design , Nuclear reactors , Gadolinium , Safety , Accidents , Neutrons , Europium , Samarium

Control Strategy of Soluble Boron-Free Operation for a Small PWR

Guangwen Bi, Chuntao Tang, Bo Yang

ICONE 2017; V003T13A007doi:https://doi.org/10.1115/ICONE25-66570

Abstract

View Articletitled, Control Strategy of Soluble Boron-Free Operation for a Small PWR

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Topics: Boron , Pressurized water reactors

Radioisotope Thermophotovoltaic Generator Design and Performance Estimates for Terrestrial Applications

Xiawa Wang, Walker Chan, Veronika Stelmakh, Peter Fisher

ICONE 2017; V003T13A008doi:https://doi.org/10.1115/ICONE25-66607

Abstract

View Articletitled, Radioisotope Thermophotovoltaic Generator Design and Performance Estimates for Terrestrial Applications

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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

Yinglin Yang, Qixun Guo, Jianshu Lin, Yaoli Zhang, Kai Ye, BoShen Bian, Zhuocheng Li

ICONE 2017; V003T13A009doi:https://doi.org/10.1115/ICONE25-66649

Abstract

View Articletitled, Modeling and Simulating Supercritical CO2 Brayton Cycle in SMR Using Modelica

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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

Huijing Jiang, Ning Bai, Huanfen Zhan, Feng Shen, Bin Gao, Xuee Wang

ICONE 2017; V003T13A010doi:https://doi.org/10.1115/ICONE25-66690

Abstract

View Articletitled, Small Modular Pressurized Water Reactors Combined With Conventional Thermal Power Plant

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Topics: Pressurized water reactors , Thermal power stations , Hybrid power systems , Steam , Superheating , Boilers , Nuclear power , Carbon , Coal , Emissions

Process Design of Heat Pump Evaporation Technology for Liquid Radioactive Waste Treatment

Jia Lu, Yan Zhou

ICONE 2017; V003T13A011doi:https://doi.org/10.1115/ICONE25-66989

Abstract

View Articletitled, Process Design of Heat Pump Evaporation Technology for Liquid Radioactive Waste Treatment

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Topics: Evaporation , Heat pumps , Process design , Radioactive wastes , Compressors , Design , Electrolytes , Energy budget (Physics) , Energy efficiency , Separation (Technology)

Application of GIS in the General Layout of a Nuclear Power Plant

Peng Fu, Ming Wang

ICONE 2017; V003T13A012doi:https://doi.org/10.1115/ICONE25-67164

Abstract

View Articletitled, Application of GIS in the General Layout of a Nuclear Power Plant

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Topics: Nuclear power stations , Design , Databases , Nuclear construction , Nuclear design , Optimization , Safety , Three-dimensional modeling

Load Following by Cogeneration: Options for Small Modular Reactors, GEN IV Reactor and Traditional Large Plants

Giorgio Locatelli, Andrea Fiordaliso, Sara Boarin, Marco Ricotti

ICONE 2017; V003T13A013doi:https://doi.org/10.1115/ICONE25-67180

Abstract

View Articletitled, Load Following by Cogeneration: Options for Small Modular Reactors, GEN IV Reactor and Traditional Large Plants

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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

Jing Hu, Xiaoping Ouyang, Zhongbing Zhang, Jinliang Liu, Liang Chen, Jinlu Ruan

ICONE 2017; V003T13A014doi:https://doi.org/10.1115/ICONE25-67249

Abstract

View Articletitled, Optical Readout Characteristics in a New Gas Scintillation Chamber for Neutron Measurement

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Topics: Neutrons , Signals , Electric fields , Wire , Particulate matter , Electrons , Gases , Photons , Protons , Resolution (Optics)

Feasibility and Implementation of the Modified Clay Technique in Control of Phaeocytstis Globosa Blooms in the Water-Intake Area of the Fangchenggang Nuclear Power Plant

Zhi-ming Yu, Kai Wang, Xi-hua Cao, Bai-zhong Wang, Xiu-xian Song, Bo-tao Xu, Fan Yu, Xin Xu

ICONE 2017; V003T13A015doi:https://doi.org/10.1115/ICONE25-67637

Abstract

View Articletitled, Feasibility and Implementation of the Modified Clay Technique in Control of Phaeocytstis Globosa Blooms in the Water-Intake Area of the Fangchenggang Nuclear Power Plant

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Topics: Nuclear power stations , Water , Emergencies

Transport Mechanism of Methane Steam Reforming on Fixed Bed Catalyst Heated by High Temperature Helium for Hydrogen Production: A CFD Investigation

Feng Wang, Jing Zhou, Qiang Wen

ICONE 2017; V003T13A016doi:https://doi.org/10.1115/ICONE25-67641

Abstract

View Articletitled, Transport Mechanism of Methane Steam Reforming on Fixed Bed Catalyst Heated by High Temperature Helium for Hydrogen Production: A CFD Investigation

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Topics: Catalysts , Computational fluid dynamics , Helium , High temperature , Hydrogen production , Methane , Steam reforming , Temperature , Very high temperature reactors , Gas cooled reactors