1-20 of 37
Systems analysis
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

Progress on the Development of DAYU3D Code for HTR Thermal-Hydraulic Design and System Analysis

Haojie Zhang, Ding She, Lei Shi
Proc. ASME. ICONE31, Volume 5: Nuclear Safety, Security, and Cyber Security; Nuclear Codes, Standards, Licensing, and Regulatory Issues, V005T06A003, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134375
https://doi.org/10.1115/ICONE31-134375
View Paper titled, Progress on the Development of DAYU3D Code for HTR Thermal-Hydraulic Design and System Analysis
Open the PDF for Progress on the Development of DAYU3D Code for HTR Thermal-Hydraulic Design and System Analysis in another window
Topics: Design, Fuels, Systems analysis, Very high temperature reactors
Proceedings Papers

Depressurization Behavior and Strategy of Automatic Depressurization System for AP1000

Zhengrun Shang, Dufeng Lv, Zhaoming Meng, Zhongning Sun
Proc. ASME. ICONE31, Volume 9: Advanced Methods of Manufacturing for Nuclear Reactors and Components; Severe Accidents and Mitigation Strategies for Beyond Design Basis Events, V009T11A011, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135645
https://doi.org/10.1115/ICONE31-135645
View Paper titled, Depressurization Behavior and Strategy of Automatic Depressurization System for AP1000
Open the PDF for Depressurization Behavior and Strategy of Automatic Depressurization System for AP1000 in another window
Topics: Accidents, Containment, Cooling, Cooling systems, Design, Loss of coolant accidents, Nuclear reactor coolants, Pipelines, Pressure, Redundancy (Engineering)
Proceedings Papers

Research on Depressurization Strategy of AP1000 Automatic Depressurization System Under DVI Pipeline Break Accident

Dufeng Lv, Zhengrun Shang, Zhaoming Meng, Zhongning Sun
Proc. ASME. ICONE31, Volume 9: Advanced Methods of Manufacturing for Nuclear Reactors and Components; Severe Accidents and Mitigation Strategies for Beyond Design Basis Events, V009T11A010, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135532
https://doi.org/10.1115/ICONE31-135532
View Paper titled, Research on Depressurization Strategy of AP1000 Automatic Depressurization System Under DVI Pipeline Break Accident
Open the PDF for Research on Depressurization Strategy of AP1000 Automatic Depressurization System Under DVI Pipeline Break Accident in another window
Topics: Accidents, Pipelines, Systems analysis
Proceedings Papers

Verification and Analysis of Thermal-Hydraulics System Program for a Power Plant Model

Lixin Du, Peng Zhou, Hao Zhang, Yanhua Yang
Proc. ASME. ICONE31, Volume 10: Risk Assessments and Management; Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V010T13A007, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134794
https://doi.org/10.1115/ICONE31-134794
View Paper titled, Verification and Analysis of Thermal-Hydraulics System Program for a Power Plant Model
Open the PDF for Verification and Analysis of Thermal-Hydraulics System Program for a Power Plant Model in another window
Topics: Accidents, Circuits, Computer software, Design, Fluids, Heat transfer, Hydraulic drive systems, Nuclear power, Nuclear power stations, Power stations
Proceedings Papers

A Chinese 300MWe Two-Loop PWR NPP LBLOCA Analysis Based on the Deterministic Realistic Hybrid Methodology

Yuhan Li, Bo Kuang
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A009, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92431
https://doi.org/10.1115/ICONE29-92431
View Paper titled, A Chinese 300MWe Two-Loop PWR NPP LBLOCA Analysis Based on the Deterministic Realistic Hybrid Methodology
Open the PDF for A Chinese 300MWe Two-Loop PWR NPP LBLOCA Analysis Based on the Deterministic Realistic Hybrid Methodology in another window
Topics: Nuclear power stations, Pressurized water reactors, Safety, Accidents, Life extension, Uncertainty, China, Cladding systems (Building), Coolants, Design
Proceedings Papers

Numerical Analysis of Pressurized Thermal Shock in Reactor Pressure Vessel

Yubin Zhang
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T08A011, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64737
https://doi.org/10.1115/ICONE28-64737
View Paper titled, Numerical Analysis of Pressurized Thermal Shock in Reactor Pressure Vessel
Open the PDF for Numerical Analysis of Pressurized Thermal Shock in Reactor Pressure Vessel in another window
Topics: Numerical analysis, Reactor vessels, Thermal shock, Accidents, Computational fluid dynamics, Computer software, Coolants, Flow (Dynamics), Mechanical structures, Nozzles
Proceedings Papers

The Interfacial Area Weighted Area-Averaged Gas Velocity Model for the Interfacial Area Transport Equation in the System Analysis Code

Mengsi Shen, Meng Lin
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A025, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64196
https://doi.org/10.1115/ICONE28-64196
View Paper titled, The Interfacial Area Weighted Area-Averaged Gas Velocity Model for the Interfacial Area Transport Equation in the System Analysis Code
Open the PDF for The Interfacial Area Weighted Area-Averaged Gas Velocity Model for the Interfacial Area Transport Equation in the System Analysis Code in another window
Topics: Systems analysis, Bubbly flow, Bubbles, Fluids, Interface structure, Slug flows
Proceedings Papers

The Choose of Decay Heat Removal Systems of SFR

Nina Yue, Rong Cai, Yun Wang, Suizheng Qiu, Dalin Zhang
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A053, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81563
https://doi.org/10.1115/ICONE26-81563
View Paper titled, The Choose of Decay Heat Removal Systems of SFR
Open the PDF for The Choose of Decay Heat Removal Systems of SFR in another window
Topics: Heat, Sodium fast reactors, Cooling systems, Accidents, Flow (Dynamics), Heat exchangers, Nuclear reactors, Safety, Sodium, Systems analysis
Proceedings Papers

Transient Thermal Behaviors of SBO Accident for a 200MW OFNP Under Heaving Motion Conditions

Qiqi Yan, Simin Luo, Yapei Zhang, Limin Liu, Guanghui Su, Suizheng Qiu
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A028, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81880
https://doi.org/10.1115/ICONE26-81880
View Paper titled, Transient Thermal Behaviors of SBO Accident for a 200MW OFNP Under Heaving Motion Conditions
Open the PDF for Transient Thermal Behaviors of SBO Accident for a 200MW OFNP Under Heaving Motion Conditions in another window
Topics: Accidents, Transients (Dynamics), Nuclear reactors, Oceans, Pressurized water reactors, Automobiles, Boats, Computer programming, Nuclear power stations, Ocean engineering
Proceedings Papers

The Design of Data Structure and Interface for Nuclear Emergency Assessment and Decision Support System

Yang Yapeng, Wei Hong, Feng Zongyang, Jia Linsheng, Xu Xiaoxiao, Zhang Jiangang
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A029, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81885
https://doi.org/10.1115/ICONE26-81885
View Paper titled, The Design of Data Structure and Interface for Nuclear Emergency Assessment and Decision Support System
Open the PDF for The Design of Data Structure and Interface for Nuclear Emergency Assessment and Decision Support System in another window
Topics: Design, Emergencies, Damage assessment, Flow charts, Nuclear power stations, Systems analysis
Proceedings Papers

Considerations on a Validation Matrix for System Analysis Codes of Pebble Bed Modular HTRs

Feng Gou, Fubing Chen, Yujie Dong
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A044, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67492
https://doi.org/10.1115/ICONE25-67492
View Paper titled, Considerations on a Validation Matrix for System Analysis Codes of Pebble Bed Modular HTRs
Open the PDF for Considerations on a Validation Matrix for System Analysis Codes of Pebble Bed Modular HTRs in another window
Topics: Systems analysis, Accidents, China, Design, High temperature, Power stations, Regulations, Safety, Thermal hydraulics
Proceedings Papers

A New Reliability Optimization Allocation Method for Nuclear Power Systems Based on Goal Oriented Methodology

Yi Xiao-jian, Xie Yong-cheng, Shi Jian, Mu Hui-na, Hou Peng
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, V001T01A043, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67777
https://doi.org/10.1115/ICONE25-67777
View Paper titled, A New Reliability Optimization Allocation Method for Nuclear Power Systems Based on Goal Oriented Methodology
Open the PDF for A New Reliability Optimization Allocation Method for Nuclear Power Systems Based on Goal Oriented Methodology in another window
Topics: Nuclear power, Optimization, Reliability, Design, Nuclear power stations, Systems analysis
Proceedings Papers

A New Reliability Assessment Method for Complex Nuclear Power Equipment Based on Goal Oriented Methodology

Yi Xiao-jian, Lu Ming-chao, Mu Hui-na, Shi Jian, Hou Peng
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, V001T01A040, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67546
https://doi.org/10.1115/ICONE25-67546
View Paper titled, A New Reliability Assessment Method for Complex Nuclear Power Equipment Based on Goal Oriented Methodology
Open the PDF for A New Reliability Assessment Method for Complex Nuclear Power Equipment Based on Goal Oriented Methodology in another window
Topics: Nuclear power, Reliability, Failure, Control systems, Event history analysis, Monte Carlo methods, Nuclear power stations, Systems analysis
Proceedings Papers

Analytical and Experimental Study on CAP1000 Guide Tube Assembly

Guohong Xue, Ming Zhang, Zhai Zhang, Jiaming Luan
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A002, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66014
https://doi.org/10.1115/ICONE25-66014
View Paper titled, Analytical and Experimental Study on CAP1000 Guide Tube Assembly
Open the PDF for Analytical and Experimental Study on CAP1000 Guide Tube Assembly in another window
Topics: Crude oil, Finite element model, Manufacturing, Modeling, Pins (Engineering), Shapes, Stiffness, Systems analysis
Proceedings Papers

Start-Up Simulation of the Improved TOPAZ-II Space Power System

Wenwen Zhang, Wenxi Tian, Suizheng Qiu, Guanghui Su
Proc. ASME. ICONE24, Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V002T06A032, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60829
https://doi.org/10.1115/ICONE24-60829
View Paper titled, Start-Up Simulation of the Improved TOPAZ-II Space Power System
Open the PDF for Start-Up Simulation of the Improved TOPAZ-II Space Power System in another window
Topics: Power systems (Machinery), Simulation, Heat pipes, Coolants, Ducts, Neutrons, Physics, Pipes, Pumps, Secondary cells
Proceedings Papers

RELAP5-3D Simulation of Natural Circulation in Fast Reactors With Lead-Bismuth Eutectic Alloy Coolant

Alex Matev
Proc. ASME. ICONE24, Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V002T06A028, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60734
https://doi.org/10.1115/ICONE24-60734
View Paper titled, RELAP5-3D Simulation of Natural Circulation in Fast Reactors With Lead-Bismuth Eutectic Alloy Coolant
Open the PDF for RELAP5-3D Simulation of Natural Circulation in Fast Reactors With Lead-Bismuth Eutectic Alloy Coolant in another window
Topics: Coolants, Eutectic alloys, Fast neutron reactors, Simulation, Nuclear reactors, Design, Fuels, Nuclear fission, Safety, Simulation results
Proceedings Papers

Research on Severe Accident Mitigation Strategy of Injecting Into the OTSG of ACP100

Zou Zhiqiang, Zhang Ming, Deng Chunrui, Deng Jian, Xiang Qingan, Yang Zhiyi
Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T13A017, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60796
https://doi.org/10.1115/ICONE24-60796
View Paper titled, Research on Severe Accident Mitigation Strategy of Injecting Into the OTSG of ACP100
Open the PDF for Research on Severe Accident Mitigation Strategy of Injecting Into the OTSG of ACP100 in another window
Topics: Accidents, China, Design, Water, Accident management, Boilers, Creep, Heat, Nuclear reactor coolants, Pressure
Proceedings Papers

COSINE Validation Experiment Plan: 1st Phase

Lifang Liu, Xiaoliang Fu, Zheng Du, Nan Yu, Yanhua Yang
Proc. ASME. ICONE21, Volume 4: Thermal Hydraulics, V004T09A015, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15171
https://doi.org/10.1115/ICONE21-15171
View Paper titled, COSINE Validation Experiment Plan: 1st Phase
Open the PDF for COSINE Validation Experiment Plan: 1st Phase in another window
Topics: China, Computer software, Containment, Cores (Molding materials), Databases, Design, Engines, Nuclear design, Physics, Systems analysis
Proceedings Papers

Experimental Validation for Specific Thermal Hydraulic Phenomena of SMART

Young-Jong Chung, Won Jae Lee, Jaejoo Ha
Proc. ASME. ICONE21, Volume 4: Thermal Hydraulics, V004T09A016, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15172
https://doi.org/10.1115/ICONE21-15172
View Paper titled, Experimental Validation for Specific Thermal Hydraulic Phenomena of SMART
Open the PDF for Experimental Validation for Specific Thermal Hydraulic Phenomena of SMART in another window
Topics: Databases, Design, Electric power generation, Flow (Dynamics), Heat transfer, Licensing, Light water reactors, Manufacturing, Safety, Seawater
Proceedings Papers

The Document Management of Major Scientific Projection of Fusion

Shenji Wang, Xiaofeng Fu, Minyou Ye, Jia Li, Meijing Gong
Proc. ASME. ICONE21, Volume 5: Fuel Cycle, Radioactive Waste Management and Decommissioning; Reactor Physics and Transport Theory; Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls; Fusion Engineering, V005T12A016, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16853
https://doi.org/10.1115/ICONE21-16853
View Paper titled, The Document Management of Major Scientific Projection of Fusion
Open the PDF for The Document Management of Major Scientific Projection of Fusion in another window
Topics: China, Collaboration, Conceptual design, Construction, Design, Nuclear fission, Nuclear power, Plasma physics, Power stations, Radiation (Physics)