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Proceedings Papers

Simulation Analysis of Main and Auxiliary Switching and Motor Starting in Nuclear Power Plants

Zhang Xingzhen, Sun Hui
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A052, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92755
https://doi.org/10.1115/ICONE29-92755
View Paper titled, Simulation Analysis of Main and Auxiliary Switching and Motor Starting in Nuclear Power Plants
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Topics: Motors, Nuclear power stations, Simulation, Simulation analysis, Stress
Proceedings Papers

Development and Verification of Thermal-Hydraulic Constitutive Model for Rectangular Channel

Yun Fei Feng, Lei Li, Ya Jie Nie, Xin Jiao, Jian Yi Li, Si Jia Meng, Ying Hao Li
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A026, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92795
https://doi.org/10.1115/ICONE29-92795
View Paper titled, Development and Verification of Thermal-Hydraulic Constitutive Model for Rectangular Channel
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Topics: Accidents, Constitutive equations, Critical heat flux, Flow (Dynamics), Fuels, Heart failure, Heat transfer, Heat transfer coefficients, Low temperature, Nuclear reactors
Proceedings Papers

Quantitative Probabilistic Safety Analysis of Locking Mechanism of Nuclear Power Control System Products

Zhirui Jiang
Proc. ASME. ICONE29, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A019, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92012
https://doi.org/10.1115/ICONE29-92012
View Paper titled, Quantitative Probabilistic Safety Analysis of Locking Mechanism of Nuclear Power Control System Products
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Topics: Control systems, Nuclear power, Probabilistic safety assessment, Simulation, Algorithms, Failure, Failure mechanisms, Probability, Reliability, Deformation
Proceedings Papers

Seismic Analysis of the Scale Reactor Structure Model of a Lead-Bismuth-Cooled ADS Reactor

Gang Rong, He Zhu, Yi Yang
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A017, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91753
https://doi.org/10.1115/ICONE29-91753
View Paper titled, Seismic Analysis of the Scale Reactor Structure Model of a Lead-Bismuth-Cooled ADS Reactor
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Topics: Seismic analysis, Annulus, Design, Fluid structure interaction, Leakage, Cavities, Finite element analysis, Fluids, Metals, Shells
Proceedings Papers

Simulation Analysis and Optimization of Lubricating Oil System

Qiongxiao Wu, Jianjun Wang, Jingming Chen, Pengzheng Li
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A053, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64547
https://doi.org/10.1115/ICONE28-64547
View Paper titled, Simulation Analysis and Optimization of Lubricating Oil System
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Topics: Flow (Dynamics), Lubricating oils, Optimization, Pressure, Simulation analysis
Proceedings Papers

Simulation Analysis on the Pressurizer Degassing Sub-System of Module Small Reactor (ACP100)

Cai Zhiyun, Ren Yun, Lai Jianyong, Zhang Yulong, Liu Hang, Liu Xianghong, Liu Minghao, Ye Zhu
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T11A007, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16341
https://doi.org/10.1115/ICONE2020-16341
View Paper titled, Simulation Analysis on the Pressurizer Degassing Sub-System of Module Small Reactor (ACP100)
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Topics: Equilibrium (Physics), Simulation analysis, Transients (Dynamics), Flow (Dynamics), Nuclear reactor coolants, Pressure, Safety, Valves, Water, Boundary-value problems
Proceedings Papers

Diffusion Law and Simulation Analysis of Radon in Uranium Tailings Based on Multiple Gauss Plume Model

Jiaxin Wang, Guohua Wu, Liguo Zhang, Jingyuan Qu, Jiejuan Tong
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A008, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81189
https://doi.org/10.1115/ICONE26-81189
View Paper titled, Diffusion Law and Simulation Analysis of Radon in Uranium Tailings Based on Multiple Gauss Plume Model
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Topics: Diffusion (Physics), Plumes (Fluid dynamics), Simulation analysis, Uranium, Wind velocity, Hazards, Pollution, Radiation (Physics), Stability
Proceedings Papers

Numerical Simulation of Debris Bed Relocation Behavior in Sodium-Cooled Fast Reactor

Chunming Teng, Bin Zhang, Jianqiang Shan
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A044, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82493
https://doi.org/10.1115/ICONE26-82493
View Paper titled, Numerical Simulation of Debris Bed Relocation Behavior in Sodium-Cooled Fast Reactor
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Topics: Computer simulation, Sodium fast reactors, Particulate matter, Shear strength, Fuels, Accidents, Boiling, Coolants, Cooling, Density
Proceedings Papers

Control Strategy Investigation for a Multi-Purpose Modular Small Pressurized Water Reactor With Once-Through Steam Generators

Qian Ma, Peiwei Sun
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, V001T13A008, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81318
https://doi.org/10.1115/ICONE26-81318
View Paper titled, Control Strategy Investigation for a Multi-Purpose Modular Small Pressurized Water Reactor With Once-Through Steam Generators
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Topics: Boilers, Pressurized water reactors, Feedwater, Flow (Dynamics), Steam, Stress, Turbines, Coolants, Pressure vessels, China
Proceedings Papers

Evaluation of Local Damage to Reinforced Concrete Panels Subjected to Oblique Impact of Rigid and Soft Missiles

Akemi Nishida, Minoru Nagai, Haruji Tsubota, Yinsheng Li
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A034, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82615
https://doi.org/10.1115/ICONE26-82615
View Paper titled, Evaluation of Local Damage to Reinforced Concrete Panels Subjected to Oblique Impact of Rigid and Soft Missiles
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Topics: Damage, Missiles, Reinforced concrete, Impact testing, Simulation results, Simulation, Simulation analysis, Stiffness
Proceedings Papers

Design Investigation on Flow Diffuser With Code_Saturne : CFD Simulation Analysis

Tingting Xu, Jiesheng Min, Serge Bellet, Richard Howard, Dominique Alvarez, Guofei Chen
Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A053, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67767
https://doi.org/10.1115/ICONE25-67767
View Paper titled, Design Investigation on Flow Diffuser With Code_Saturne : CFD Simulation Analysis
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Topics: Computational fluid dynamics, Design, Diffusers, Flow (Dynamics), Simulation analysis, Simulation, Engineering simulation, Algorithms, Computers, Coolants
Proceedings Papers

A Study for Evaluating Local Damage to Reinforced Concrete Panels Subjected to Oblique Impact: Part 2 — Simulation Analysis of the Experimental Results of Local Damage Caused by Impact of Deformable Projectiles

Akemi Nishida, Yoshimi Ohta, Haruji Tsubota, Yinsheng Li
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A012, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66142
https://doi.org/10.1115/ICONE25-66142
View Paper titled, A Study for Evaluating Local Damage to Reinforced Concrete Panels Subjected to Oblique Impact: Part 2 — Simulation Analysis of the Experimental Results of Local Damage Caused by Impact of Deformable Projectiles
Open the PDF for A Study for Evaluating Local Damage to Reinforced Concrete Panels Subjected to Oblique Impact: Part 2 — Simulation Analysis of the Experimental Results of Local Damage Caused by Impact of Deformable Projectiles in another window
Topics: Damage, Projectiles, Reinforced concrete, Simulation analysis, Impact testing, Simulation results, Internal energy (Physics), Stress
Proceedings Papers

A Study for Evaluating Local Damage to Reinforced Concrete Panels Subjected to Oblique Impact: Part 3 — Simulation Analysis for Evaluating Perforation Phenomena Caused by Oblique Impact of Deformable Projectiles

Haruji Tsubota, Yoshimi Ohta, Akemi Nishida, Yinsheng Li
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A017, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66179
https://doi.org/10.1115/ICONE25-66179
View Paper titled, A Study for Evaluating Local Damage to Reinforced Concrete Panels Subjected to Oblique Impact: Part 3 — Simulation Analysis for Evaluating Perforation Phenomena Caused by Oblique Impact of Deformable Projectiles
Open the PDF for A Study for Evaluating Local Damage to Reinforced Concrete Panels Subjected to Oblique Impact: Part 3 — Simulation Analysis for Evaluating Perforation Phenomena Caused by Oblique Impact of Deformable Projectiles in another window
Topics: Damage, Projectiles, Reinforced concrete, Simulation analysis, Simulation results, Concretes, Energy transformation, Friction, Rupture
Proceedings Papers

Root Cause Analysis of Pipeline Rupture in the Condensate Extraction System of Nuclear Power Plant

Chen Qiang, Han Ning, Chen Weihan, Che Yinhui
Proc. ASME. ICONE25, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle and Balance of Plant; I&C, Digital Controls, and Influence of Human Factors, V001T01A046, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67860
https://doi.org/10.1115/ICONE25-67860
View Paper titled, Root Cause Analysis of Pipeline Rupture in the Condensate Extraction System of Nuclear Power Plant
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Topics: Condensed matter, Nuclear power stations, Pipelines, Root cause analysis, Rupture, Failure mechanisms, Pressurized water reactors, Circuits, Corrective actions, Corrosion
Proceedings Papers

Transient Simulation Modeling of Condenser Based on Thermal System Dynamics

Qiu Jinrong, Lin Yuansheng
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A115, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67789
https://doi.org/10.1115/ICONE25-67789
View Paper titled, Transient Simulation Modeling of Condenser Based on Thermal System Dynamics
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Topics: Computer simulation, Condensers (steam plant), Dynamics (Mechanics), Thermal systems, Transients (Dynamics), Differential equations, Flow (Dynamics), Heat transfer, Mass transfer, Modeling
Proceedings Papers

Performance Test and Simulation Study on the Air Path of CAP1400 Passive Containment Cooling System

Pan Xinxin, Huang Jingyu, Song Chunjing
Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A011, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66321
https://doi.org/10.1115/ICONE25-66321
View Paper titled, Performance Test and Simulation Study on the Air Path of CAP1400 Passive Containment Cooling System
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Topics: Containment, Cooling systems, Simulation, Testing performance, Air flow, Wind, Computational fluid dynamics, Wind tunnels, Annulus, Wind velocity
Proceedings Papers

Newly Developed Coupling Scheme in RMC With Internal Thermal Feedback and OTF Doppler-Broadening Method

Ouwen Yexin, Shanfang Huang, Kan Wang
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A014, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66519
https://doi.org/10.1115/ICONE25-66519
View Paper titled, Newly Developed Coupling Scheme in RMC With Internal Thermal Feedback and OTF Doppler-Broadening Method
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Topics: Feedback, Nuclear reactors, Steady state, Fuels, Hydraulics, Manufacturing, Physics, Pressurized water reactors, Simulation, Simulation analysis
Proceedings Papers

Turbulent Flow Boundary Layer and Heat Transfer Characteristics for the Intermediate Heat-Exchanger Simulation of a VHTR

Yannan Wu, Yujie Dong, Kun Yuan
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T05A017, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30436
https://doi.org/10.1115/ICONE22-30436
View Paper titled, Turbulent Flow Boundary Layer and Heat Transfer Characteristics for the Intermediate Heat-Exchanger Simulation of a VHTR
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Topics: Boundary layers, Heat exchangers, Heat transfer, Simulation, Turbulence, Very high temperature reactors, Fluids, Friction, High pressure (Physics), High temperature
Proceedings Papers

RELAP5 Code Analysis of LSTF Small Break LOCA Tests With Steam Generator Intentional Depressurization as an Accident Management Procedure: Investigation on Base Case Result Appropriate for the Best Estimate Plus Uncertainty (BEPU) Application

Ikuo Kinoshita, Toshihide Torige, Michio Murase, Yoshitaka Yoshida, Takeshi Takeda, Akira Satou, Hideo Nakamura
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T06A022, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30559
https://doi.org/10.1115/ICONE22-30559
View Paper titled, RELAP5 Code Analysis of LSTF Small Break LOCA Tests With Steam Generator Intentional Depressurization as an Accident Management Procedure: Investigation on Base Case Result Appropriate for the Best Estimate Plus Uncertainty (BEPU) Application
Open the PDF for RELAP5 Code Analysis of LSTF Small Break LOCA Tests With Steam Generator Intentional Depressurization as an Accident Management Procedure: Investigation on Base Case Result Appropriate for the Best Estimate Plus Uncertainty (BEPU) Application in another window
Topics: Accident management, Boilers, Uncertainty, Accidents, Condensation, Coolants, Flow (Dynamics), High pressure (Physics), Pressure, Simulation analysis
Proceedings Papers

HTR-PM Simulation Analysis of Accident Conditions Based on vPower Platform

Tang Yang, Yangping Zhou, Zhiwei Zhou, Zhang Dabin
Proc. ASME. ICONE22, Volume 6: Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I&C); Fusion Engineering; Beyond Design Basis Events, V006T15A025, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30726
https://doi.org/10.1115/ICONE22-30726
View Paper titled, HTR-PM Simulation Analysis of Accident Conditions Based on vPower Platform
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Topics: Accidents, Simulation analysis, Boilers, Cycles, Design, Energy generation, Flow (Dynamics), Helium, Safety, Simulation