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Proceedings Papers

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
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A025, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66700
https://doi.org/10.1115/ICONE25-66700
View Paper titled, 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
Proceedings Papers

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
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A057, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67531
https://doi.org/10.1115/ICONE25-67531
View Paper titled, 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
Proceedings Papers

Three Dimensional Modeling of the Thermo-Mechanical Performance of the Fuel Rods of a PWR

Wang Zhu, Zhang Chunyu, Li Aolin, Yuan Cenxi
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A001, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66010
https://doi.org/10.1115/ICONE25-66010
View Paper titled, Three Dimensional Modeling of the Thermo-Mechanical Performance of the Fuel Rods of a PWR
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Topics: Fuel rods, Pressurized water reactors, Thermomechanics, Three-dimensional modeling, Stress, Temperature, Accidents, Cladding systems (Building), Displacement, Finite element analysis
Proceedings Papers

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

Weiyan Yang, Chuntao Tang, Hongbo Zhang, Bo Yang
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A017, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66567
https://doi.org/10.1115/ICONE25-66567
View Paper titled, Numerical Comparison and Analysis of Nuclear Core Design Code System SCAP and MPACT
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Topics: Design, Nuclear power stations, Boron, Cycles, Electrical measurement, Nuclear engineering, Simulation
Proceedings Papers

Small Punch Test on Mechanical Properties of Molybdenum Single Crystal Weld

Yan Ma, Jianju Wang, Jinyun Lei
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A033, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66824
https://doi.org/10.1115/ICONE25-66824
View Paper titled, 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
Proceedings Papers

The Effect of MA Transmutation in the PWR on Fuel Cycle

Haoyang Yu, Bin Liu, Wenxin Zhang, Jin Cai
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A065, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67787
https://doi.org/10.1115/ICONE25-67787
View Paper titled, 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
Proceedings Papers

A New Numerical Method for Fuel Temperature Calculation

Jin Xin, Xiaohan Liu, Xiaoyan Wei
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A009, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66248
https://doi.org/10.1115/ICONE25-66248
View Paper titled, 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
Proceedings Papers

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

Zhou Qin, Li Jiwei, Dang Yu, Ding Yang
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A041, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67112
https://doi.org/10.1115/ICONE25-67112
View Paper titled, 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
Proceedings Papers

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

Yining Zhang, Haochun Zhang, Yang Su, Guangbo Zhao
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A049, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67275
https://doi.org/10.1115/ICONE25-67275
View Paper titled, A Comparative Study of 10 Different Methods on Numerical Solving of Point Reactor Neutron Kinetics Equations
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Topics: Neutrons, Errors, Polynomials, Runge-Kutta methods, Gears, Computer simulation, Density, Nuclear power stations, Nuclear reactors, Stiffness
Proceedings Papers

A Novel Method for Solving Reactor Physics Diffusion and Transport Equation

Hu Wenjun, Cao Yonggang
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A002, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66045
https://doi.org/10.1115/ICONE25-66045
View Paper titled, 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
Proceedings Papers

The Sensitivity Simulation of Different Geometric Pretreatment in Method of Characteristics

Tian XiaoRui, Zhou Tao, Li Zichao, Yu Tao
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A058, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67565
https://doi.org/10.1115/ICONE25-67565
View Paper titled, The Sensitivity Simulation of Different Geometric Pretreatment in Method of Characteristics
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Topics: Simulation, Simulation results, Physics, Storage
Proceedings Papers

Development and Verification of the PWR Lattice Code PANDA

Hongbo Zhang, Chuntao Tang, Weiyan Yang, Guangwen Bi, Bo Yang
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A018, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66573
https://doi.org/10.1115/ICONE25-66573
View Paper titled, 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
Proceedings Papers

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
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A026, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66747
https://doi.org/10.1115/ICONE25-66747
View Paper titled, 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
Proceedings Papers

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

Yingming Song, Qingyu Gao, Ke Wang, Yaping Guo, Lu Zhang, Yongwei Yang
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A010, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66314
https://doi.org/10.1115/ICONE25-66314
View Paper titled, 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
Proceedings Papers

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

Jozef Molnar, Marek Pecka, Jaroslav Kment
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A034, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66867
https://doi.org/10.1115/ICONE25-66867
View Paper titled, SCORPIO-VVER: Two Decades of Experience and Enhancements in Reactor Core Monitoring and Surveillance in Central Europe
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Topics: Surveillance, Fuels, Construction, Monitoring systems, Nuclear power stations, Computation, Computers, Design, Education, Engineers
Proceedings Papers

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
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A042, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67128
https://doi.org/10.1115/ICONE25-67128
View Paper titled, 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
Proceedings Papers

The Rigorous SP3 Theory and Study on its Numerical Verification

Pan Qingquan, Lu Haoliang, Li Dongsheng, Wang Kan
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A050, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67309
https://doi.org/10.1115/ICONE25-67309
View Paper titled, The Rigorous SP3 Theory and Study on its Numerical Verification
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Topics: Approximation, Boundary-value problems, Leakage, Scalars
Proceedings Papers

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
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A027, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66774
https://doi.org/10.1115/ICONE25-66774
View Paper titled, Simulation on Pellet-Cladding Mechanical Interaction (PCMI) of Accident Tolerant Fuel (ATF) With Coated Cladding
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Topics: Accidents, Cladding systems (Building), Fuels, Simulation, Coatings, Zirconium, Alloys, Fuel rods, Pressure, Stress
Proceedings Papers

Out-of-Pile Properties Investigation of UO 2 -BeO Fuel Pellet

Jiwei Li, Yang Ding, Wentao Liu, Guangwen Bi, Ruirui Zhao, Qin Zhou
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A019, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66585
https://doi.org/10.1115/ICONE25-66585
View Paper titled, Out-of-Pile Properties Investigation of UO 2 -BeO Fuel Pellet
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Topics: Fuels, Thermal conductivity, Elastic moduli, Thermal expansion, Uranium, Composite materials, Nuclear power stations, Sintering
Proceedings Papers

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

Zheng Zheng, Hui Li, Mengqi Wang
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A011, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66401
https://doi.org/10.1115/ICONE25-66401
View Paper titled, 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