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Proceedings Papers

Eigenvalue Implicit Sensitivity Calculation and Analysis for Lattice-Physics Calculation

Yong Liu, Liangzhi Cao, Hongchun Wu, Tiejun Zu, Qingming He
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T02A019, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60401
https://doi.org/10.1115/ICONE24-60401
View Paper titled, Eigenvalue Implicit Sensitivity Calculation and Analysis for Lattice-Physics Calculation
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Topics: Eigenvalues, Physics, Resonance, Uncertainty analysis, Boiling water reactors, Computational methods, Cross section (Physics), Light water reactors, Nuclear fission, Nuclides
Proceedings Papers

The Influence of Microstructures on the Thermal Conductivity of Polycrystalline UO 2

Enze Jin, Chen Liu, Heming He
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T02A028, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-61093
https://doi.org/10.1115/ICONE24-61093
View Paper titled, The Influence of Microstructures on the Thermal Conductivity of Polycrystalline UO 2
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Topics: Thermal conductivity, Grain size, Design, Finite element methods, Fuels, Irradiation (Radiation exposure), Porosity
Proceedings Papers

Oxygen Used as an Oxidizer in Acid In-Situ Leach Uranium: From Theory to Practice

Wensheng Liao, Yahui Tan, Limin Wang, Jianhua Li
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T02A010, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60126
https://doi.org/10.1115/ICONE24-60126
View Paper titled, Oxygen Used as an Oxidizer in Acid In-Situ Leach Uranium: From Theory to Practice
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Topics: Oxygen, Uranium, Pressure, Aluminum, Minerals, Precipitation, Hydrogen, Iron, Testing
Proceedings Papers

A Numerical Solution to the Point Kinetic Equations Using Diagonally Implicit Runge Kutta Method

Zhizhu Zhang, Yun Cai
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T02A001, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60011
https://doi.org/10.1115/ICONE24-60011
View Paper titled, A Numerical Solution to the Point Kinetic Equations Using Diagonally Implicit Runge Kutta Method
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Topics: Computation, Differential equations, Runge-Kutta methods, Stiffness
Proceedings Papers

Hydraulic Balance Characteristics of an Innovative Bottom Nozzle Design With Angled Trailing Edge

Wenchi Yu
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T02A029, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-61130
https://doi.org/10.1115/ICONE24-61130
View Paper titled, Hydraulic Balance Characteristics of an Innovative Bottom Nozzle Design With Angled Trailing Edge
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Topics: Design, Nozzles, Flow (Dynamics), Pressure drop, Computational fluid dynamics, Nuclear fuels
Proceedings Papers

MOCUM Code Verification and Sensibility Study Using C5G7 Benchmark

Xue Yang, Rajan Borse, Nader Satvat
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T02A020, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60443
https://doi.org/10.1115/ICONE24-60443
View Paper titled, MOCUM Code Verification and Sensibility Study Using C5G7 Benchmark
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Topics: Errors, Geometry, Manufacturing, Neutron flux, Screw threads, Simulation, Thread
Proceedings Papers

The Preliminary Performance Study of ATF With M3 Fuel and Zr-4 Cladding

Yin Chunyu, Tu Teng, Changbing Tang, Yongjun Jiao
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T02A011, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60150
https://doi.org/10.1115/ICONE24-60150
View Paper titled, The Preliminary Performance Study of ATF With M3 Fuel and Zr-4 Cladding
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Topics: Cladding systems (Building), Fuels, Zirconium, Accidents, Carbon, Coating processes, Coatings, Design, Failure, Failure mechanisms
Proceedings Papers

Analysis and Prospect of the Duplex Fuel Pellets of LOWI Type for Water-Cooled Reactors

Songyang Li, Dingqu Wang, Wenli Guo, Yueyuan Jiang
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T02A021, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60505
https://doi.org/10.1115/ICONE24-60505
View Paper titled, Analysis and Prospect of the Duplex Fuel Pellets of LOWI Type for Water-Cooled Reactors
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Topics: Fuels, Water, Design, Manufacturing, Nuclear fuels, Power density, Temperature, Annulus, Cutting, Geometry
Proceedings Papers

Mechanism Study and Numerical Simulation on Blistering of Plate-Type Fuel

Yangbin Deng, Dalin Zhang, Qing Lu, Yingwei Wu, Wenxi Tian, Suizheng Qiu, G. H. Su
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T02A022, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60583
https://doi.org/10.1115/ICONE24-60583
View Paper titled, Mechanism Study and Numerical Simulation on Blistering of Plate-Type Fuel
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Topics: Computer simulation, Fuels, Cladding systems (Building), Plates (structures), Power density, Computational fluid dynamics, Damage, Deformation, Delays, Fuel rods
Proceedings Papers

Neutron Up-Scattering Effect in Refined Energy Group Structure

Qingming He, Hongchun Wu, Yunzhao Li, Liangzhi Cao, Tiejun Zu
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T02A013, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60313
https://doi.org/10.1115/ICONE24-60313
View Paper titled, Neutron Up-Scattering Effect in Refined Energy Group Structure
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Topics: Electromagnetic scattering, Neutrons, Radiation scattering, Scattering (Physics), S-matrix theory, Absorption, Cladding systems (Building), Cross section (Physics), Fuels, Resonance
Proceedings Papers

Preliminary Investigation of Physical Characteristics in a New Power Ramp Test Irradiation Rig

Liang Zhang, Liqing Qiu, Mingyan Tong
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T02A004, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60052
https://doi.org/10.1115/ICONE24-60052
View Paper titled, Preliminary Investigation of Physical Characteristics in a New Power Ramp Test Irradiation Rig
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Topics: Irradiation (Radiation exposure), Fuel rods, Fuels, Neutrons, Pressure, Computational methods, Curve fitting, Density, Heat, Neutron flux
Proceedings Papers

Development of Plenum Temperature Model for Accident Analysis

Wenjie Li, Yongjun Jiao, Bingde Chen
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T02A014, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60330
https://doi.org/10.1115/ICONE24-60330
View Paper titled, Development of Plenum Temperature Model for Accident Analysis
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Topics: Accidents, Temperature, Fuels, Heat transfer, Light water reactors, Computer software, Design, Fuel rods, Pressure, Resolution (Optics)
Proceedings Papers

Activation Analysis of the Reactor Pressure Vessel of HTR-PM Reactor Using FLUKA Code

Sheng Fang, Wenqian Li, Sida Sun, Hong Li
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T02A023, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60627
https://doi.org/10.1115/ICONE24-60627
View Paper titled, Activation Analysis of the Reactor Pressure Vessel of HTR-PM Reactor Using FLUKA Code
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Topics: Activation analysis, Reactor vessels, Maintenance, High temperature, Irradiation (Radiation exposure), Metals, Nuclides, Radiation sources, Radioisotopes
Proceedings Papers

Lattice Boltzmann Method for Solving Time-Dependent Radiation Transport and Reactor Criticality Problems

A. Gairola, Hitesh Bindra, Gaurav Agarwal, Suneet Singh
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T02A005, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60058
https://doi.org/10.1115/ICONE24-60058
View Paper titled, Lattice Boltzmann Method for Solving Time-Dependent Radiation Transport and Reactor Criticality Problems
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Topics: Lattice Boltzmann methods, Radiation (Physics), Neutrons, Electromagnetic scattering, Radiation scattering, Scattering (Physics), Dynamics (Mechanics)
Proceedings Papers

The Generation of Few-Group Constants for Fast Reactor Analysis

Xianan Du, Liangzhi Cao, Youqi Zheng
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T02A015, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60331
https://doi.org/10.1115/ICONE24-60331
View Paper titled, The Generation of Few-Group Constants for Fast Reactor Analysis
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Topics: Fast neutron reactors, Collapse, Anisotropy, Cross section (Physics), Electromagnetic scattering, Neutrons, Radiation scattering, Scattering (Physics), Spectra (Spectroscopy)
Proceedings Papers

Orientation Relationships of Delta Hydrides in Zirconium and Zircaloy-4

Anton Pshenichnikov, Juri Stuckert
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T02A006, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60061
https://doi.org/10.1115/ICONE24-60061
View Paper titled, Orientation Relationships of Delta Hydrides in Zirconium and Zircaloy-4
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Topics: Zirconium, Diffraction, Electron backscatter diffraction, Electrons, Grain boundaries, Spectra (Spectroscopy)
Proceedings Papers

Preliminary Benchmark Validation of a Lattice Physics Code COSLATC

Tongrui Yang, Zhanquan Liu, Yuhang Yan, Shuo Li, Hui Yu, Yixue Chen
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T02A024, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60659
https://doi.org/10.1115/ICONE24-60659
View Paper titled, Preliminary Benchmark Validation of a Lattice Physics Code COSLATC
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Topics: Physics, Fuels, Pressurized water reactors, Cores (Molding materials), Design, Engines, Manufacturing, Nuclear engineering, Nuclear power, Software development
Proceedings Papers

The Powerful MOC Module in Advanced Neutronics Lattice Code GALAXY

Xiaoming Chai, Xiaolan Tu, Wei Lu
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T02A025, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60661
https://doi.org/10.1115/ICONE24-60661
View Paper titled, The Powerful MOC Module in Advanced Neutronics Lattice Code GALAXY
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Topics: Boundary-value problems, China, Computation, Geometry, Neutrons, Nuclear power, Shapes, Trajectories (Physics)
Proceedings Papers

Measurements of Fine Structures in the Lead-Bismuth Eutectic Alloy Melts by Differential Scanning Calorimetry

Changqing Ye, Qiulin Li, Ping Wu, Guoyi Tang, Wei Liu
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T02A016, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60338
https://doi.org/10.1115/ICONE24-60338
View Paper titled, Measurements of Fine Structures in the Lead-Bismuth Eutectic Alloy Melts by Differential Scanning Calorimetry
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Topics: Differential scanning calorimetry, Eutectic alloys, Alloys, Signals, Embrittlement, Melting point, Steel, Temperature, Generation IV reactors, Melting
Proceedings Papers

Improvement on the Manufacture of UO 2 Pellet

Hao Fu
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T02A007, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60089
https://doi.org/10.1115/ICONE24-60089
View Paper titled, Improvement on the Manufacture of UO 2 Pellet
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Topics: Cavities, Density, Grinding, Manufacturing, Manufacturing technology, Pressure