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Proceedings Papers

Calculation Method and Analysis on Thermal Compressor Ejection Characteristics

Huiqiang Xu, Shoubao Dai, Na Sun, Lin Sun, Yanqing Wang

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A018, August 8–12, 2022

Paper No: ICONE29-92689

DOI: https://doi.org/10.1115/ICONE29-92689

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Topics: Compressors, Computational methods

Proceedings Papers

Optimization for Rapid Dose Calculation of the RIMPUFF Model and Its Evaluation Against Belgian Field Experiment

Li Yang, Xinpeng Li, Yixue Chen, Boxin Wang, Sheng Fang

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A014, August 8–12, 2022

Paper No: ICONE29-90806

DOI: https://doi.org/10.1115/ICONE29-90806

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Topics: Interpolation, Optimization, Computational methods, Databases, Emergencies

Proceedings Papers

Overview of AFCEN Non-Linear Benchmark in China – Improving Rules for Vessel Ratcheting Evaluation

Yu Tan, Xuejiao Shao, Enming Liang, Shuchun Zuo, Feng Lv, Thomas Metais, Han Liu

Proc. ASME. ICONE29, Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues, V006T06A015, August 8–12, 2022

Paper No: ICONE29-93561

DOI: https://doi.org/10.1115/ICONE29-93561

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Topics: China, Vessels, Bullets, Computational methods, Computer software, Evaluation methods, Fatigue, Fatigue analysis, Geometry, Nozzles

Proceedings Papers

Modal analysis and additional fluid mass of coaxial three-layer thin-wall member in annular flow gap

Chaofan Zhang, Daogang Lu, Yu Liu, Haotian Qiu

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A036, August 8–12, 2022

Paper No: ICONE29-92274

DOI: https://doi.org/10.1115/ICONE29-92274

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Topics: Cylinders, Flow (Dynamics), Fluids, Modal analysis, Thin wall structures, Fast neutron reactors, Shells, Pumps, Water, Clearances (Engineering)

Proceedings Papers

Parameter Calculation Method of Porous Media Based on BP Neural Network

Fei Zhao, Daogang Lu, Yu Liu, Dong Liu, Jiliang Xu, Jinghui Wu, Fei Xie, Yuchao Wang

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A089, August 8–12, 2022

Paper No: ICONE29-92382

DOI: https://doi.org/10.1115/ICONE29-92382

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Topics: Artificial neural networks, Computational methods, Fluid structure interaction, Porous materials

Proceedings Papers

A New Safety Margin Evaluation Method: Quality Margin Method

Zhao Minfu, Duan Minghui, Lv Yufeng

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A003, August 4–5, 2020

Paper No: ICONE2020-16031

DOI: https://doi.org/10.1115/ICONE2020-16031

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Topics: Critical heat flux, Evaluation methods, Safety, Design, Heat, Nucleate boiling, Accidents, Computational methods, Flux (Metallurgy), Heating

Proceedings Papers

Experimental Study on Multi-Channel Jets in Plate Assembly Under Blockage Condition

Huang Huijian, Wang Peng, Li Dongyang, Sichao Tan

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A058, August 4–5, 2020

Paper No: ICONE2020-16955

DOI: https://doi.org/10.1115/ICONE2020-16955

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Topics: Jets, Manufacturing, Flow (Dynamics), Computational methods, Coolants, Flowmeters, Fuels, Pressure, Reynolds number, Tensors

Proceedings Papers

Development of an Efficient Tool for Evaluating Dose at Through-Holes

Tatsuya Watanabe, Hironobu Iwanami, Tomoharu Hashimoto, Ryuichi Tayama

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A060, August 4–5, 2020

Paper No: ICONE2020-16931

DOI: https://doi.org/10.1115/ICONE2020-16931

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Topics: Cables, Computation, Computational methods, Design, Ducts, Electromagnetic scattering, Gamma rays, Nuclear power stations, Particulate matter, Radiation scattering

Proceedings Papers

Condition Fault Tree: An Extension of Traditional Fault Tree to Handle Uncertainty

Zhenxu Zhou, Qin Zhang

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A014, July 22–26, 2018

Paper No: ICONE26-81243

DOI: https://doi.org/10.1115/ICONE26-81243

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Topics: Uncertainty, Gates (Closures), Computational methods, Fourier transform spectroscopy, Probability, Reliability

Proceedings Papers

Study on the Shaking Dynamic Response of Steam Generator LOCA

Qian Huang, Xiaofei Yu, Huanhuan Qi, Naibin Jiang, Fengchun Cai, Zhipeng Feng

Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A009, July 22–26, 2018

Paper No: ICONE26-81278

DOI: https://doi.org/10.1115/ICONE26-81278

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Topics: Boilers, Dynamic response, Dynamic response analysis, Nuclear power stations, Nuclear reactor coolants, Stress, Accidents, China, Computational methods, Coolants

Proceedings Papers

Real-Time Online Risk Monitoring and Management Method for Maintenance Optimization in Nuclear Power Plant

Anqi Xu, Zhijian Zhang, HuaZhi Zhang, Min Zhang, He Wang, Yingfei Ma, Sijuan Chen, Yan Wang, Gangyang Zheng

Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T14A021, July 22–26, 2018

Paper No: ICONE26-82472

DOI: https://doi.org/10.1115/ICONE26-82472

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Topics: Maintenance, Nuclear power stations, Optimization, Risk monitoring, Risk, Risk assessment, Errors, Modeling, Computational methods, Control systems

Proceedings Papers

Assessment of Control Room Radiological Habitability of High-Temperature Reactor Pebble-Bed Module in Shidao Bay Multi-Reactor Nuclear Power Site

Xinpeng Li, Sheng Fang

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A042, July 22–26, 2018

Paper No: ICONE26-82448

DOI: https://doi.org/10.1115/ICONE26-82448

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Topics: Control rooms, High temperature, Nuclear power, Design, Accidents, China, Computational methods, Coolants, Licensing, Meteorology

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

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

Proceedings Papers

Research on Algorithm of Sump Level Operator Assisted Support Program for PWR Nuclear Power Plant

Liu Qiaofen, Xiao Sanping, Liu Yu, Liu Xichao, Jiang Xulun

Proc. ASME. ICONE26, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs, V001T04A012, July 22–26, 2018

Paper No: ICONE26-81714

DOI: https://doi.org/10.1115/ICONE26-81714

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Topics: Algorithms, Nuclear power stations, Pressurized water reactors, Leakage flows, Computational methods, Leakage, Leak-before-break, Nuclear reactor coolants, Nuclear reactor safety

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

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Topics: Approximation, Computational methods, Cross section (Physics), Density, Design, Errors, Geometry, Manufacturing, Modeling, Neutron flux

Proceedings Papers

A Neutron Transport Calculation Method for Deep Penetration and its Preliminary Verification

Wankui Yang, Baoxin Yuan, Songbao Zhang, Haibing Guo, Yaoguang Liu, Li Deng

Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A032, July 22–26, 2018

Paper No: ICONE26-81709

DOI: https://doi.org/10.1115/ICONE26-81709

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Topics: Computational methods, Neutrons, Geometry, Modeling, Monte Carlo methods, China, Cross section (Physics), Finishes, Slabs, Tin

Proceedings Papers

Influence of Xe-135 Dynamic Behavior on Core Operation Safety for a Molten Salt Reactor

Wu Jian-hui, Li Xiao-xiao, Hu Ji-feng, Chen Jin-gen, Yu Cheng-gang, Zou Chun-yan, Cai Xiang-zhou

Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A050, July 22–26, 2018

Paper No: ICONE26-82352

DOI: https://doi.org/10.1115/ICONE26-82352

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Topics: Molten salt reactors, Safety, Neutrons, Fuels, Helium, Nuclear reactors, Absorption, Chain, Computational methods, Density

Proceedings Papers

Analysis on Radioactive Gas Movement and Delay Status Before Release

Bo Nan Zhu

Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A017, July 2–6, 2017

Paper No: ICONE25-66713

DOI: https://doi.org/10.1115/ICONE25-66713

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Topics: Delays, Activated carbon, Design, Dimensions, Flow (Dynamics), Computational methods, Design methodology, Isotopes, Nuclear fission, Nuclear power stations

Proceedings Papers

The Preliminary Shielding Analysis of CAP1400 Based on JMCT-S Code

Yan Zhou, Zheng Zheng, Qiliang Mei

Paper No: ICONE25-66429

DOI: https://doi.org/10.1115/ICONE25-66429

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Topics: Computational methods, Cycles, Design, Engineering simulation, Equilibrium (Physics), Errors, Fluence (Radiation measurement), Geometry, Modeling, Neutron sources

Proceedings Papers

Nonlinear Analysis Method Research of Multi-Bolt Connection Structure of Primary Equipment Support

Jianrong Zou, Shaochong Zhou

Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A069, July 2–6, 2017

Paper No: ICONE25-66875

DOI: https://doi.org/10.1115/ICONE25-66875

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Topics: ASME Standards, Boilers, Computational methods, Design, Engineering design, Finite element methods, Flange connections, Flanges, Girders, Junctions

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NARROW

Calculation Method and Analysis on Thermal Compressor Ejection Characteristics

Optimization for Rapid Dose Calculation of the RIMPUFF Model and Its Evaluation Against Belgian Field Experiment

Overview of AFCEN Non-Linear Benchmark in China – Improving Rules for Vessel Ratcheting Evaluation

Modal analysis and additional fluid mass of coaxial three-layer thin-wall member in annular flow gap

Parameter Calculation Method of Porous Media Based on BP Neural Network

A New Safety Margin Evaluation Method: Quality Margin Method

Experimental Study on Multi-Channel Jets in Plate Assembly Under Blockage Condition

Development of an Efficient Tool for Evaluating Dose at Through-Holes

Condition Fault Tree: An Extension of Traditional Fault Tree to Handle Uncertainty

Study on the Shaking Dynamic Response of Steam Generator LOCA

Real-Time Online Risk Monitoring and Management Method for Maintenance Optimization in Nuclear Power Plant

Assessment of Control Room Radiological Habitability of High-Temperature Reactor Pebble-Bed Module in Shidao Bay Multi-Reactor Nuclear Power Site

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

Research on Algorithm of Sump Level Operator Assisted Support Program for PWR Nuclear Power Plant

Research on Coupling Scheme of Monte Carlo Burnup Calculation in RMC

A Neutron Transport Calculation Method for Deep Penetration and its Preliminary Verification

Influence of Xe-135 Dynamic Behavior on Core Operation Safety for a Molten Salt Reactor

Analysis on Radioactive Gas Movement and Delay Status Before Release

The Preliminary Shielding Analysis of CAP1400 Based on JMCT-S Code

Nonlinear Analysis Method Research of Multi-Bolt Connection Structure of Primary Equipment Support

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