1-20 of 76
Computational methods
Close
Save search
Follow your search
Access your saved searches in your account
Would you like to receive an alert when new items match your search?
Close Modal
Sort by
Proceedings Papers

Calculation of Radiation Field and Shutdown Dose Rate for Fusion Reactor Based on cosRMC

Shichang Liu, Zhenyu Wang, Rui Che
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A027, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134661
https://doi.org/10.1115/ICONE31-134661
View Paper titled, Calculation of Radiation Field and Shutdown Dose Rate for Fusion Reactor Based on cosRMC
Open the PDF for Calculation of Radiation Field and Shutdown Dose Rate for Fusion Reactor Based on cosRMC in another window
Topics: Fusion reactors, Radiation (Physics), Algorithms, Resolution (Optics), Accuracy and precision, Computational methods, Geometry, Nuclear design, Particulate matter, Safety
Proceedings Papers

Research on Monte Carlo-Neutron Point Kernel Integration Method Coupling Calculation Method of Neutron Radiation Field

Qi Zhang, Heli Gong, Liye Liu, Yushou Song, Qinjian Cao, Jinlong Yong, Jiawen Hu
Proc. ASME. ICONE31, Volume 5: Nuclear Safety, Security, and Cyber Security; Nuclear Codes, Standards, Licensing, and Regulatory Issues, V005T05A025, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135218
https://doi.org/10.1115/ICONE31-135218
View Paper titled, Research on Monte Carlo-Neutron Point Kernel Integration Method Coupling Calculation Method of Neutron Radiation Field
Open the PDF for Research on Monte Carlo-Neutron Point Kernel Integration Method Coupling Calculation Method of Neutron Radiation Field in another window
Topics: Computational methods, Neutrons, Radiation (Physics)
Proceedings Papers

Three-Dimensional Numerical Simulation on DRACS and PRACS Heat Removal Ways of Natural Circulation Based on the PLANDTL-DHX Experimental Device

Haijie Song, Xiangfeng Ma, Haiqi Zhao, Yuhao Zhang, Daogang Lu, Xueyuan Zhang
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A108, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136974
https://doi.org/10.1115/ICONE31-136974
View Paper titled, Three-Dimensional Numerical Simulation on DRACS and PRACS Heat Removal Ways of Natural Circulation Based on the PLANDTL-DHX Experimental Device
Open the PDF for Three-Dimensional Numerical Simulation on DRACS and PRACS Heat Removal Ways of Natural Circulation Based on the PLANDTL-DHX Experimental Device in another window
Topics: Computer simulation, Heat, Sodium fast reactors, Flow (Dynamics), Cooling systems, Modeling, Computational methods, Design, Temperature
Proceedings Papers

Research and First Application of 4D Radiation Dose Calculation in China

Zhaoxing Liu, Ri Zhao, Runcheng Liang, Jing Zhang, Xin Liu, Liye Liu
Proc. ASME. ICONE31, Volume 8: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V008T09A027, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136133
https://doi.org/10.1115/ICONE31-136133
View Paper titled, Research and First Application of 4D Radiation Dose Calculation in China
Open the PDF for Research and First Application of 4D Radiation Dose Calculation in China in another window
Topics: China, Phantoms, Radiation (Physics), Algorithms, Deformation, Nuclear power stations, Computational methods, Maintenance, Nuclear industry, Reliability
Proceedings Papers

Research and Preliminary Verification of the Resonance Self-Shielding Calculation Method for the High-Fidelity Neutronics Code VITAS

Han Yin, Tengfei Zhang, Xiaojing Liu
Proc. ASME. ICONE31, Volume 10: Risk Assessments and Management; Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V010T13A002, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-133419
https://doi.org/10.1115/ICONE31-133419
View Paper titled, Research and Preliminary Verification of the Resonance Self-Shielding Calculation Method for the High-Fidelity Neutronics Code VITAS
Open the PDF for Research and Preliminary Verification of the Resonance Self-Shielding Calculation Method for the High-Fidelity Neutronics Code VITAS in another window
Topics: Computational methods, Resonance
Proceedings Papers

Study of Jet Characteristics and Structural Fatigue in the Upper Chamber of a Lead-Bismuth Eutectic Cooled Reactor Based on Fluid-Structure Coupling Methods

Ji Zhang, Mingjun Wang, Wenxi Tian, Suizheng Qiu, Guanghui Su
Proc. ASME. ICONE31, Volume 11: Student Paper Competition, V011T15A067, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135637
https://doi.org/10.1115/ICONE31-135637
View Paper titled, Study of Jet Characteristics and Structural Fatigue in the Upper Chamber of a Lead-Bismuth Eutectic Cooled Reactor Based on Fluid-Structure Coupling Methods
Open the PDF for Study of Jet Characteristics and Structural Fatigue in the Upper Chamber of a Lead-Bismuth Eutectic Cooled Reactor Based on Fluid-Structure Coupling Methods in another window
Topics: Fatigue, Fluids, Fatigue damage, Temperature, Computational methods, Design, Fatigue analysis, Flow (Dynamics), Fluctuations (Physics), Fluid structure interaction
Proceedings Papers

Research Methods and Protective Measures for Internal Flooding Analysis of Nuclear Islands

Guang Du, Danfeng Zhao, Daping Lin, Xiaoxia Chen
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A021, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135047
https://doi.org/10.1115/ICONE31-135047
View Paper titled, Research Methods and Protective Measures for Internal Flooding Analysis of Nuclear Islands
Open the PDF for Research Methods and Protective Measures for Internal Flooding Analysis of Nuclear Islands in another window
Topics: Floods, Nuclear power stations, Design, Hazards, Safety, Water, Computational methods, Engineering design, Evaluation methods, Nuclear power
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92382
https://doi.org/10.1115/ICONE29-92382
View Paper titled, Parameter Calculation Method of Porous Media Based on BP Neural Network
Open the PDF for Parameter Calculation Method of Porous Media Based on BP Neural Network in another window
Topics: Artificial neural networks, Computational methods, Fluid structure interaction, Porous materials
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90806
https://doi.org/10.1115/ICONE29-90806
View Paper titled, Optimization for Rapid Dose Calculation of the RIMPUFF Model and Its Evaluation Against Belgian Field Experiment
Open the PDF for Optimization for Rapid Dose Calculation of the RIMPUFF Model and Its Evaluation Against Belgian Field Experiment in another window
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93561
https://doi.org/10.1115/ICONE29-93561
View Paper titled, Overview of AFCEN Non-Linear Benchmark in China – Improving Rules for Vessel Ratcheting Evaluation
Open the PDF for Overview of AFCEN Non-Linear Benchmark in China – Improving Rules for Vessel Ratcheting Evaluation in another window
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92274
https://doi.org/10.1115/ICONE29-92274
View Paper titled, Modal analysis and additional fluid mass of coaxial three-layer thin-wall member in annular flow gap
Open the PDF for Modal analysis and additional fluid mass of coaxial three-layer thin-wall member in annular flow gap in another window
Topics: Cylinders, Flow (Dynamics), Fluids, Modal analysis, Thin wall structures, Fast neutron reactors, Shells, Pumps, Water, Clearances (Engineering)
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92689
https://doi.org/10.1115/ICONE29-92689
View Paper titled, Calculation Method and Analysis on Thermal Compressor Ejection Characteristics
Open the PDF for Calculation Method and Analysis on Thermal Compressor Ejection Characteristics in another window
Topics: Compressors, Computational methods
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16931
https://doi.org/10.1115/ICONE2020-16931
View Paper titled, Development of an Efficient Tool for Evaluating Dose at Through-Holes
Open the PDF for Development of an Efficient Tool for Evaluating Dose at Through-Holes in another window
Topics: Cables, Computation, Computational methods, Design, Ducts, Electromagnetic scattering, Gamma rays, Nuclear power stations, Particulate matter, Radiation scattering
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16031
https://doi.org/10.1115/ICONE2020-16031
View Paper titled, A New Safety Margin Evaluation Method: Quality Margin Method
Open the PDF for A New Safety Margin Evaluation Method: Quality Margin Method in another window
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16955
https://doi.org/10.1115/ICONE2020-16955
View Paper titled, Experimental Study on Multi-Channel Jets in Plate Assembly Under Blockage Condition
Open the PDF for Experimental Study on Multi-Channel Jets in Plate Assembly Under Blockage Condition in another window
Topics: Jets, Manufacturing, Flow (Dynamics), Computational methods, Coolants, Flowmeters, Fuels, Pressure, Reynolds number, Tensors
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
Open the PDF for Research on Coupling Scheme of Monte Carlo Burnup Calculation in RMC in another window
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81709
https://doi.org/10.1115/ICONE26-81709
View Paper titled, A Neutron Transport Calculation Method for Deep Penetration and its Preliminary Verification
Open the PDF for A Neutron Transport Calculation Method for Deep Penetration and its Preliminary Verification in another window
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82352
https://doi.org/10.1115/ICONE26-82352
View Paper titled, Influence of Xe-135 Dynamic Behavior on Core Operation Safety for a Molten Salt Reactor
Open the PDF for Influence of Xe-135 Dynamic Behavior on Core Operation Safety for a Molten Salt Reactor in another window
Topics: Molten salt reactors, Safety, Neutrons, Fuels, Helium, Nuclear reactors, Absorption, Chain, Computational methods, Density
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81243
https://doi.org/10.1115/ICONE26-81243
View Paper titled, Condition Fault Tree: An Extension of Traditional Fault Tree to Handle Uncertainty
Open the PDF for Condition Fault Tree: An Extension of Traditional Fault Tree to Handle Uncertainty in another window
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81278
https://doi.org/10.1115/ICONE26-81278
View Paper titled, Study on the Shaking Dynamic Response of Steam Generator LOCA
Open the PDF for Study on the Shaking Dynamic Response of Steam Generator LOCA in another window
Topics: Boilers, Dynamic response, Dynamic response analysis, Nuclear power stations, Nuclear reactor coolants, Stress, Accidents, China, Computational methods, Coolants