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Proceedings Papers

Light Water-Cooled High-Performance Research Reactor Physics Design and Analysis

Zihao Guo, Guang Wang, Genghua Su, Xiuan Shi
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A036, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93256
https://doi.org/10.1115/ICONE29-93256
View Paper titled, Light Water-Cooled High-Performance Research Reactor Physics Design and Analysis
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Topics: Design, Irradiation (Radiation exposure), Neutron flux, Physics, Water, Biomedicine, Isotopes, Cycles, Decontamination, Fuels
Proceedings Papers

Active Interrogation of Highly Enriched Uranium in the Suitcase by Using NG-9 Neutron Generator

Guang-Yu Shi, Shi-Wei Jing
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A015, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89597
https://doi.org/10.1115/ICONE29-89597
View Paper titled, Active Interrogation of Highly Enriched Uranium in the Suitcase by Using NG-9 Neutron Generator
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Topics: Neutron flux, Neutron generators, Uranium
Proceedings Papers

Design of Radiation Damage Monitoring Scheme for Materials in China Experimental Fast Reactor

Hu Ziao, Chen Xiao-xian, Chen Xiao-liang
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A010, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90146
https://doi.org/10.1115/ICONE29-90146
View Paper titled, Design of Radiation Damage Monitoring Scheme for Materials in China Experimental Fast Reactor
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Topics: China, Damage, Design, Fast neutron reactors, Irradiation (Radiation exposure), Neutron flux, Radiation damage, Sensors, Neutrons, Cladding systems (Building)
Proceedings Papers

A Preliminary Study on Neutronic Performance of the Spallation Target With the Proton Beam Variation

Junjie Zhou, Qin Zeng, Jinchen Yang, Yi Yang, Ying Shi, Yanyi Jiang
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T03A004, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64388
https://doi.org/10.1115/ICONE28-64388
View Paper titled, A Preliminary Study on Neutronic Performance of the Spallation Target With the Proton Beam Variation
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Topics: Neutron flux, Proton beams, Spallation (Nuclear physics)
Proceedings Papers

Numerical Simulation of Multi-Physics Processes in Nuclear System Based on Galerkin Finite Element Method

Baoxin Yuan, Wankui Yang, Songbao Zhang, Bin Zhong, Junxia Wei, Yangjun Ying
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T02A005, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16801
https://doi.org/10.1115/ICONE2020-16801
View Paper titled, Numerical Simulation of Multi-Physics Processes in Nuclear System Based on Galerkin Finite Element Method
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Topics: Computer simulation, Finite element methods, Physics, Heat, Heat transfer, Temperature, Thermoelasticity, Finite element analysis, Neutron flux, Neutrons
Proceedings Papers

The Experimental Research on the Mechanical Characteristics of the Newly Designed Fuel Rod Supporting Structure of Spacer Grid

Quan-yao Ren, Zeng-ping Pu, Mei-yin Zheng, Jie Chen, Mian Qin, Yuan-Ji Han, Yuan Peng, Ping Chen, Rui-rui Zhao, Jian-wei Li
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T05A004, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16121
https://doi.org/10.1115/ICONE2020-16121
View Paper titled, The Experimental Research on the Mechanical Characteristics of the Newly Designed Fuel Rod Supporting Structure of Spacer Grid
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Topics: Deformation, Fuel rods, Mechanical properties, Springs, Stress, Deflection, Manufacturing, Neutron flux, Strips
Proceedings Papers

Improvement of the Evaluation Accuracy for the Diameter Prediction of the CANDU Pressure Tubes

Jong Yeob Jung
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T09A007, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16590
https://doi.org/10.1115/ICONE2020-16590
View Paper titled, Improvement of the Evaluation Accuracy for the Diameter Prediction of the CANDU Pressure Tubes
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Topics: Pressure, Creep, Fuels, Irradiation (Radiation exposure), Modeling, Cooling, Deformation, Flow (Dynamics), Heat, Heat transfer
Proceedings Papers

Proportional-Integral Disturbance Observer of Nuclear Reactors

Zhe Dong
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T06A008, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16207
https://doi.org/10.1115/ICONE2020-16207
View Paper titled, Proportional-Integral Disturbance Observer of Nuclear Reactors
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Topics: Nuclear reactors, Coolants, Computer simulation, Errors, Heating, Neutron flux, Neutrons, Steady state, Temperature, Theoretical analysis
Proceedings Papers

A Preliminary Study on Neutronic Performance of the Spallation Target With the Proton Beam Variation

Junjie Zhou, Qin Zeng, Jinchen Yang, Yi Yang, Ying Shi, Yanyi Jiang
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T11A010, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16427
https://doi.org/10.1115/ICONE2020-16427
View Paper titled, A Preliminary Study on Neutronic Performance of the Spallation Target With the Proton Beam Variation
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Topics: Neutron flux, Proton beams, Spallation (Nuclear physics)
Proceedings Papers

Core Design Study of Super FBR With Multi-Axial Fuel Shuffling and Different Coolant Density

Shogo Noda, Sukarman Sukarman, Akifumi Yamaji, Tetsuo Takei, Takanari Fukuda, Arisa Ayukawa
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A011, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81501
https://doi.org/10.1115/ICONE26-81501
View Paper titled, Core Design Study of Super FBR With Multi-Axial Fuel Shuffling and Different Coolant Density
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Topics: Coolants, Density, Design, Fuels, Breeder reactors, Collisions (Physics), Neutron flux, Neutrons, Probability, Temperature
Proceedings Papers

Axial Flux Wire Measurements at the McMaster Nuclear Reactor

E. L. MacConnachie, D. R. Novog, S. E. Day
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A086, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82412
https://doi.org/10.1115/ICONE26-82412
View Paper titled, Axial Flux Wire Measurements at the McMaster Nuclear Reactor
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Topics: Nuclear reactors, Wire, Irradiation (Radiation exposure), Uncertainty, Neutron flux, Diffusion (Physics), Neutron activation analysis, Neutrons, Nuclear power, Particulate matter
Proceedings Papers

Research on Coupling Scheme of Monte Carlo Burnup Calculation in RMC

Wanlin Li, Kan Wang, Ganglin Yu, Yaodong Li
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A005, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81140
https://doi.org/10.1115/ICONE26-81140
View Paper titled, Research on Coupling Scheme of Monte Carlo Burnup Calculation in RMC
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Topics: Approximation, Computational methods, Cross section (Physics), Density, Design, Errors, Geometry, Manufacturing, Modeling, Neutron flux
Proceedings Papers

One Step Method for Multigroup Adjoint Neutron Flux Through Continuous Energy Monte Carlo Calculation

Xiaotong Shang, Guanlin Shi, Kan Wang
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A043, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82185
https://doi.org/10.1115/ICONE26-82185
View Paper titled, One Step Method for Multigroup Adjoint Neutron Flux Through Continuous Energy Monte Carlo Calculation
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Topics: Neutron flux, Neutrons, Nuclear fission, Transients (Dynamics), Cross section (Physics), Event history analysis, Monte Carlo methods, Nuclear reactor kinetics, Probability, Transient analysis
Proceedings Papers

Physics Design of Special Epithermal Neutron Beam Based on Multi D-D Reaction Neutron Tubes

Yi Yang, Yiguo Li, Bin Zhao
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A019, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81392
https://doi.org/10.1115/ICONE26-81392
View Paper titled, Physics Design of Special Epithermal Neutron Beam Based on Multi D-D Reaction Neutron Tubes
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Topics: Design, Neutron beams, Neutrons, Physics, Irradiation (Radiation exposure), Neutron sources, Contamination, Neutron generators, Boron, Cancer
Proceedings Papers

Buildup and Decay Analysis of Corrosion Products Activity in Primary Coolant Loop of AP-1000

Fiaz Mahmood, Huasi Hu, Liangzhi Cao
Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A008, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81388
https://doi.org/10.1115/ICONE26-81388
View Paper titled, Buildup and Decay Analysis of Corrosion Products Activity in Primary Coolant Loop of AP-1000
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Topics: Coolants, Corrosion, Cyber-physical systems, Radiation (Physics), Design, Emergencies, Half-life, Matlab, Neutron flux, Pressurized water reactors
Proceedings Papers

Verification of Shielding Calculation Capability of RMC With H.B.Robinson-2 Pressure Vessel Benchmark

Junjie Rao, Xiaotong Shang, Kan Wang
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A010, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81694
https://doi.org/10.1115/ICONE26-81694
View Paper titled, Verification of Shielding Calculation Capability of RMC With H.B.Robinson-2 Pressure Vessel Benchmark
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Topics: Pressure vessels, Computational methods, Neutron flux, Neutrons, Nuclear fission, Cavities, China, Neutron sources, Nuclear fuel cycle, Teams
Proceedings Papers

Conceptual Core Design of Breeding BWR

Rui Guo, Akifumi Yamaji
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A024, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66829
https://doi.org/10.1115/ICONE25-66829
View Paper titled, Conceptual Core Design of Breeding BWR
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Topics: Boiling water reactors, Design, Water, Light water reactors, Fuels, Manufacturing, Neutrons, Atoms, Coolants, Cooling
Proceedings Papers

The Activation Sources of Reactor Internals During Decommissioning

Jianchun Han, Yan Zhou, Hui Li, Qiliang Mei
Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A008, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66430
https://doi.org/10.1115/ICONE25-66430
View Paper titled, The Activation Sources of Reactor Internals During Decommissioning
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Topics: Nuclear decommissioning, Neutrons, Nuclear power stations, Neutron flux, Nuclides, Pressurized water reactors, Contamination, Irradiation (Radiation exposure), Modeling, Radiation (Physics)
Proceedings Papers

Application of Monte Carlo to PWR Cavity Radiation Streaming Calculation

Han Jingru, Liu Qiaofeng, Chen Haiying, Zhang Chunming
Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A039, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67831
https://doi.org/10.1115/ICONE25-67831
View Paper titled, Application of Monte Carlo to PWR Cavity Radiation Streaming Calculation
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Topics: Cavities, Pressurized water reactors, Radiation (Physics), Monte Carlo methods, Simulation, Geometry, Accuracy and precision, Errors, Leakage, Neutron beams
Proceedings Papers

Coupled Analysis of Thermal Hydraulics and Neutronics for a Molten Salt Reactor

Jian Ge, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G. H. Su
Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A036, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67042
https://doi.org/10.1115/ICONE25-67042
View Paper titled, Coupled Analysis of Thermal Hydraulics and Neutronics for a Molten Salt Reactor
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Topics: Molten salt reactors, Thermal hydraulics, Neutrons, Computational fluid dynamics, Coolants, Design, Diffusion (Physics), Finite volume methods, Momentum, Neutron flux