Search Results | ICONE | ASME Digital Collection

1-20 of 95

2 3 4 5

Sort by

Sort Order Select

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

Paper No: ICONE29-89597

DOI: https://doi.org/10.1115/ICONE29-89597

View Paper

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

Paper No: ICONE29-90146

DOI: https://doi.org/10.1115/ICONE29-90146

View Paper

Topics: China, Damage, Design, Fast neutron reactors, Irradiation (Radiation exposure), Neutron flux, Radiation damage, Sensors, Neutrons, Cladding systems (Building)

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

Paper No: ICONE29-93256

DOI: https://doi.org/10.1115/ICONE29-93256

View Paper

Topics: Design, Irradiation (Radiation exposure), Neutron flux, Physics, Water, Biomedicine, Isotopes, Cycles, Decontamination, Fuels

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

Paper No: ICONE28-64388

DOI: https://doi.org/10.1115/ICONE28-64388

View Paper

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

Paper No: ICONE2020-16801

DOI: https://doi.org/10.1115/ICONE2020-16801

View Paper

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

Paper No: ICONE2020-16121

DOI: https://doi.org/10.1115/ICONE2020-16121

View Paper

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

Paper No: ICONE2020-16590

DOI: https://doi.org/10.1115/ICONE2020-16590

View Paper

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

Paper No: ICONE2020-16207

DOI: https://doi.org/10.1115/ICONE2020-16207

View Paper

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

Paper No: ICONE2020-16427

DOI: https://doi.org/10.1115/ICONE2020-16427

View Paper

Topics: Neutron flux, Proton beams, Spallation (Nuclear physics)

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

Paper No: ICONE26-81392

DOI: https://doi.org/10.1115/ICONE26-81392

View Paper

Topics: Design, Neutron beams, Neutrons, Physics, Irradiation (Radiation exposure), Neutron sources, Contamination, Neutron generators, Boron, Cancer

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

Paper No: ICONE26-82412

DOI: https://doi.org/10.1115/ICONE26-82412

View Paper

Topics: Nuclear reactors, Wire, Irradiation (Radiation exposure), Uncertainty, Neutron flux, Diffusion (Physics), Neutron activation analysis, Neutrons, Nuclear power, Particulate matter

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

Paper No: ICONE26-81388

DOI: https://doi.org/10.1115/ICONE26-81388

View Paper

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

Paper No: ICONE26-81694

DOI: https://doi.org/10.1115/ICONE26-81694

View Paper

Topics: Pressure vessels, Computational methods, Neutron flux, Neutrons, Nuclear fission, Cavities, China, Neutron sources, Nuclear fuel cycle, Teams

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

Paper No: ICONE26-81501

DOI: https://doi.org/10.1115/ICONE26-81501

View Paper

Topics: Coolants, Density, Design, Fuels, Breeder reactors, Collisions (Physics), Neutron flux, Neutrons, Probability, Temperature

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

Paper No: ICONE26-81140

DOI: https://doi.org/10.1115/ICONE26-81140

View Paper

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

Paper No: ICONE26-82185

DOI: https://doi.org/10.1115/ICONE26-82185

View Paper

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

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

Paper No: ICONE25-66430

DOI: https://doi.org/10.1115/ICONE25-66430

View Paper

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

Paper No: ICONE25-67831

DOI: https://doi.org/10.1115/ICONE25-67831

View Paper

Topics: Cavities, Pressurized water reactors, Radiation (Physics), Monte Carlo methods, Simulation, Geometry, Accuracy and precision, Errors, Leakage, Neutron beams

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

Paper No: ICONE25-66314

DOI: https://doi.org/10.1115/ICONE25-66314

View Paper

Topics: Neutrons, Simulation, Spacetime, Neutron flux, Temperature, Transients (Dynamics), Approximation, Coolants, Fuels, Physics

Proceedings Papers

Physical Design on PMNSR With LEU Core

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

Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A060, July 2–6, 2017

Paper No: ICONE25-67580

DOI: https://doi.org/10.1115/ICONE25-67580

View Paper

Topics: Design, Fuels, Neutron flux, Uranium, Coolants, Engineering prototypes, Error analysis, Irradiation (Radiation exposure), Manufacturing, Neutron sources

2 3 4 5

NARROW

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

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

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

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

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

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

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

Proportional-Integral Disturbance Observer of Nuclear Reactors

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

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

Axial Flux Wire Measurements at the McMaster Nuclear Reactor

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

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

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

Research on Coupling Scheme of Monte Carlo Burnup Calculation in RMC

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

The Activation Sources of Reactor Internals During Decommissioning

Application of Monte Carlo to PWR Cavity Radiation Streaming Calculation

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

Physical Design on PMNSR With LEU Core

Journals

Conference Proceedings

eBooks

Resources

Opportunities

Journals

Conference Proceedings

eBooks

Resources

Opportunities

This Feature Is Available To Subscribers Only