1-20 of 951
Pressurized water reactors
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

Research on Spacing Design Method of Condenser Half-Side Operation in Pressurized Water Reactor Nuclear Power Plant

Zhao Qingsen, Liang Junqin, Zhou Shuai, Chen Jie, Zeng Weipeng, Zhang Qiang
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A071, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93265
https://doi.org/10.1115/ICONE29-93265
View Paper titled, Research on Spacing Design Method of Condenser Half-Side Operation in Pressurized Water Reactor Nuclear Power Plant
Open the PDF for Research on Spacing Design Method of Condenser Half-Side Operation in Pressurized Water Reactor Nuclear Power Plant in another window
Topics: Condensers (steam plant), Cooling, Design methodology, Nuclear power stations, Pipes, Pressurized water reactors
Proceedings Papers

Safety Evaluation of Flowrate Dissymmetry on Nuclear Power Plant Operation

Dongyuan Li, Jinkai Wang, Jiaoshen Xu, Zengpei Zhu, Yaqi Zhang
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A072, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93277
https://doi.org/10.1115/ICONE29-93277
View Paper titled, Safety Evaluation of Flowrate Dissymmetry on Nuclear Power Plant Operation
Open the PDF for Safety Evaluation of Flowrate Dissymmetry on Nuclear Power Plant Operation in another window
Topics: Nuclear power plant operations, Nuclear reactor coolants, Nucleate boiling, Safety, Accidents, Flow (Dynamics), Nuclear power stations, Pressurized water reactors, Feedwater, Steam
Proceedings Papers

Study on the Applicability of Flat Ceramic Membrane in Simulated Primary Coolant Water Environment of PWR Nuclear Power Plant

Yuxin Guan, Jiguo Chen, Guodong Zhang, Xuqiu Ren
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A033, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92184
https://doi.org/10.1115/ICONE29-92184
View Paper titled, Study on the Applicability of Flat Ceramic Membrane in Simulated Primary Coolant Water Environment of PWR Nuclear Power Plant
Open the PDF for Study on the Applicability of Flat Ceramic Membrane in Simulated Primary Coolant Water Environment of PWR Nuclear Power Plant in another window
Topics: Ceramics, Coolants, Membranes, Nuclear power stations, Pressurized water reactors, Water
Proceedings Papers

Research on Signal Reconstruction Technology for Nuclear Power Plant Based on Self-Associative Kernel Regression

Zhuang Miao, Fangxiaozhi Yu, Zhao Xu
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A006, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89258
https://doi.org/10.1115/ICONE29-89258
View Paper titled, Research on Signal Reconstruction Technology for Nuclear Power Plant Based on Self-Associative Kernel Regression
Open the PDF for Research on Signal Reconstruction Technology for Nuclear Power Plant Based on Self-Associative Kernel Regression in another window
Topics: Nuclear power stations, Sensors, Signal reconstruction, Instrumentation, Control systems, Pressurized water reactors, Reliability, Signals, Steam
Proceedings Papers

Research on Precision Water Reactor Fuel Servo Operation System

Li Ping, Peiqiang Deng, Wei Qian, Kaiyu Yang, Jiansong Zhai, Shuiyang Huang
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A041, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92493
https://doi.org/10.1115/ICONE29-92493
View Paper titled, Research on Precision Water Reactor Fuel Servo Operation System
Open the PDF for Research on Precision Water Reactor Fuel Servo Operation System in another window
Topics: Nuclear fuels, Nuclear power stations, Servomechanisms, Water, Engines, Motors, Permanent magnets, Algorithms, Control algorithms, Control theory
Proceedings Papers

Investigation of the Fuel Element Damage Monitoring Technology in HTGRs and PWRs

Rui Nie, Yu Wang, Feng Xie, Shan Qing, Jianzhu Cao
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A002, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-88883
https://doi.org/10.1115/ICONE29-88883
View Paper titled, Investigation of the Fuel Element Damage Monitoring Technology in HTGRs and PWRs
Open the PDF for Investigation of the Fuel Element Damage Monitoring Technology in HTGRs and PWRs in another window
Topics: Damage, Fuels, Nuclides, Pressurized water reactors, Very high temperature reactors
Proceedings Papers

Research on Scenarios and Development Paths of China’s Commercial Closed Nuclear Fuel Cycle

Min Xiao, Xiaojun Xiao
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A007, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89223
https://doi.org/10.1115/ICONE29-89223
View Paper titled, Research on Scenarios and Development Paths of China’s Commercial Closed Nuclear Fuel Cycle
Open the PDF for Research on Scenarios and Development Paths of China’s Commercial Closed Nuclear Fuel Cycle in another window
Topics: Nuclear fuel cycle, Pressurized water reactors
Proceedings Papers

Research on the Influence of Degassing on the Release of Fission Gases in PWRs

Yaoxin Ye, Pengtao Fu, Zhijun Li
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A008, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89461
https://doi.org/10.1115/ICONE29-89461
View Paper titled, Research on the Influence of Degassing on the Release of Fission Gases in PWRs
Open the PDF for Research on the Influence of Degassing on the Release of Fission Gases in PWRs in another window
Topics: Failure, Fuels, Gases, Nuclear fission, Pressurized water reactors, Coolants, Nuclear power stations, Cladding systems (Building), Nuclear fuel cycle, Rods
Proceedings Papers

PWR Spent Fuel Dry Storage Loading Pattern and Safety Evaluation

Li Wen, Gao Jinghui, Li Gang, Zhong Shengdong, Xu Jin, Zhao Bingquan
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A078, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93351
https://doi.org/10.1115/ICONE29-93351
View Paper titled, PWR Spent Fuel Dry Storage Loading Pattern and Safety Evaluation
Open the PDF for PWR Spent Fuel Dry Storage Loading Pattern and Safety Evaluation in another window
Topics: Pressurized water reactors, Safety, Spent nuclear fuels, Storage
Proceedings Papers

Risk Monitoring of Spurious Safety Injection in Pressurized Water Reactor Nuclear Power Plants

Yu Huang, Zhenying Jiao, Zhenying Wang, Taike Wang, Kaihe Kong, Min Li, Jianwen Zhang
Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A019, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92126
https://doi.org/10.1115/ICONE29-92126
View Paper titled, Risk Monitoring of Spurious Safety Injection in Pressurized Water Reactor Nuclear Power Plants
Open the PDF for Risk Monitoring of Spurious Safety Injection in Pressurized Water Reactor Nuclear Power Plants in another window
Topics: Accidents, Nuclear power stations, Pressurized water reactors, Risk monitoring, Safety
Proceedings Papers

Design Improvement of the Discharge Proposal Preventing SG Overfill After SGTR in HPR1000 PWR

Qinghua Li, Jun Fang, Yafei Li, Bin Zhao, Guangfei Wang
Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A035, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93093
https://doi.org/10.1115/ICONE29-93093
View Paper titled, Design Improvement of the Discharge Proposal Preventing SG Overfill After SGTR in HPR1000 PWR
Open the PDF for Design Improvement of the Discharge Proposal Preventing SG Overfill After SGTR in HPR1000 PWR in another window
Topics: Accidents, Design, Flow (Dynamics), Pipelines, Pressurized water reactors, Safety, Boilers, Fluids, Pressure, Testing performance
Proceedings Papers

Construction and Application of Mitigation System Performance Index (MSPI) Platform for a China Nuclear Power Plant

Jie Zhang, Jing Wang, Peiying Zhang, Kun Tan, Minxue Yang
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A024, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91837
https://doi.org/10.1115/ICONE29-91837
View Paper titled, Construction and Application of Mitigation System Performance Index (MSPI) Platform for a China Nuclear Power Plant
Open the PDF for Construction and Application of Mitigation System Performance Index (MSPI) Platform for a China Nuclear Power Plant in another window
Topics: China, Construction, Nuclear power stations, Water, Safety, Risk, Accidents, Maintenance, Pressurized water reactors, Cooling
Proceedings Papers

Prediction and Uncertainty Analysis of Stress Corrosion Fraction Failure Probability for Pressurized Water Reactor Materials

Deyan Kong, Xu Liu, Jie Cheng, Jianjun Wang, Jinqiang Zhang, Dingyong Chen, Qingzhao Li, Yanting Liu
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A029, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91951
https://doi.org/10.1115/ICONE29-91951
View Paper titled, Prediction and Uncertainty Analysis of Stress Corrosion Fraction Failure Probability for Pressurized Water Reactor Materials
Open the PDF for Prediction and Uncertainty Analysis of Stress Corrosion Fraction Failure Probability for Pressurized Water Reactor Materials in another window
Topics: Chaos, Failure, Polynomials, Pressurized water reactors, Probability, Stress corrosion cracking, Uncertainty analysis
Proceedings Papers

Initiating Events Analysis in Operating Phase for Pressurized Water Reactor Nuclear Power Plant

Feng Chu-ran, Ma Yuan, Yan Lin, Yang Guansan, Liu Bin
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A051, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93295
https://doi.org/10.1115/ICONE29-93295
View Paper titled, Initiating Events Analysis in Operating Phase for Pressurized Water Reactor Nuclear Power Plant
Open the PDF for Initiating Events Analysis in Operating Phase for Pressurized Water Reactor Nuclear Power Plant in another window
Topics: Nuclear power stations, Pressurized water reactors, Statistical analysis, Design, Damage, Decision making, Errors, Event history analysis, Failure, Model development
Proceedings Papers

Numerical Investigation on Heat Transfer Features of Gas-Cooled Open Lattice Reactor in Normal Operations

Junlin Fang, Qian Sun, Yu Ji, Zishen Ye, Jun Sun, Zhe Sui
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A105, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92925
https://doi.org/10.1115/ICONE29-92925
View Paper titled, Numerical Investigation on Heat Transfer Features of Gas-Cooled Open Lattice Reactor in Normal Operations
Open the PDF for Numerical Investigation on Heat Transfer Features of Gas-Cooled Open Lattice Reactor in Normal Operations in another window
Topics: Gas flow, Heat conduction, Heat transfer, Thermal radiation, Convection, Design, Fuel rods, Pressurized water reactors, Radiation (Physics), Sodium fast reactors
Proceedings Papers

Multiphysics Analysis of Fuel Performance and Tritium Migration in FeCrAl and Cr-Coated Zircalloy Cladding Under PWR Normal Operating and Transient Conditions

Rong Liu, Liwen Yang, Shengyu Liu
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A069, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91981
https://doi.org/10.1115/ICONE29-91981
View Paper titled, Multiphysics Analysis of Fuel Performance and Tritium Migration in FeCrAl and Cr-Coated Zircalloy Cladding Under PWR Normal Operating and Transient Conditions
Open the PDF for Multiphysics Analysis of Fuel Performance and Tritium Migration in FeCrAl and Cr-Coated Zircalloy Cladding Under PWR Normal Operating and Transient Conditions in another window
Topics: Cladding systems (Building), Fuels, Pressurized water reactors, Transients (Dynamics)
Proceedings Papers

Rod Ejection Accident Simulation of a Small Pressurized Water Reactor

Ziqi Fan, Peiwei Sun, Xinyu Wei
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A062, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91878
https://doi.org/10.1115/ICONE29-91878
View Paper titled, Rod Ejection Accident Simulation of a Small Pressurized Water Reactor
Open the PDF for Rod Ejection Accident Simulation of a Small Pressurized Water Reactor in another window
Topics: Accidents, Pressurized water reactors, Simulation
Proceedings Papers

Modeling and Simulation of a Pressurized Water Reactor Nuclear Power Plant and Power System

Haomin Wang, Xinyu Wei
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A042, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91413
https://doi.org/10.1115/ICONE29-91413
View Paper titled, Modeling and Simulation of a Pressurized Water Reactor Nuclear Power Plant and Power System
Open the PDF for Modeling and Simulation of a Pressurized Water Reactor Nuclear Power Plant and Power System in another window
Topics: Dynamic models, Modeling, Nuclear power stations, Power systems (Machinery), Pressurized water reactors, Simulation
Proceedings Papers

Determination of Control Rod Position by Global Optimization Methods

Zhang Qian, Zhihong Liu, Jing Zhao
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A100, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92637
https://doi.org/10.1115/ICONE29-92637
View Paper titled, Determination of Control Rod Position by Global Optimization Methods
Open the PDF for Determination of Control Rod Position by Global Optimization Methods in another window
Topics: Algorithms, Optimization, Pressurized water reactors, Sensors, Computer software, Genetic algorithms, Inverse problems, Neutrons, Particle swarm optimization, Physics
Proceedings Papers

Analysis of Severe Accident Induced by Loss of Coolant Accident for a Small Pressurized Water Reactor

Xiaolong Bi, Peiwei Sun, Xinyu Wei
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A083, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92167
https://doi.org/10.1115/ICONE29-92167
View Paper titled, Analysis of Severe Accident Induced by Loss of Coolant Accident for a Small Pressurized Water Reactor
Open the PDF for Analysis of Severe Accident Induced by Loss of Coolant Accident for a Small Pressurized Water Reactor in another window
Topics: Accidents, Coolants, Pressurized water reactors