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

Optimization of the Tritium Production and Discharge in HPR1000

Pengtao Fu, Mingliang Dai
Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A033, August 8–12, 2022
Paper No: ICONE29-92816
https://doi.org/10.1115/ICONE29-92816
View Paper titled, Optimization of the Tritium Production and Discharge in HPR1000
Open the PDF for Optimization of the Tritium Production and Discharge in HPR1000 in another window
Topics: Boron, Conformity assessment, Coolants, Cycles, Design, Neutron sources, Optimization, Pressurized water reactors, Radioactivity, Radioisotopes
Proceedings Papers

Study on Passive Pulse Cooling Method of Secondary Side in PWR Nuclear Power Plant

Zhenhua Wu, Junjun Xu, Weijin Wang, Runcheng Li, Qi Tang
Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A020, August 8–12, 2022
Paper No: ICONE29-93049
https://doi.org/10.1115/ICONE29-93049
View Paper titled, Study on Passive Pulse Cooling Method of Secondary Side in PWR Nuclear Power Plant
Open the PDF for Study on Passive Pulse Cooling Method of Secondary Side in PWR Nuclear Power Plant in another window
Topics: Cooling, Nuclear power stations, Pressurized water reactors
Proceedings Papers

Research on Operating Strategy of Total Loss of Essential Service Water System With RHR Not Connected in PWR Unit

Shengtao Zhang, Ke Yi
Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A010, August 8–12, 2022
Paper No: ICONE29-91810
https://doi.org/10.1115/ICONE29-91810
View Paper titled, Research on Operating Strategy of Total Loss of Essential Service Water System With RHR Not Connected in PWR Unit
Open the PDF for Research on Operating Strategy of Total Loss of Essential Service Water System With RHR Not Connected in PWR Unit in another window
Topics: Pressurized water reactors, Water
Proceedings Papers

Assessment on Accident and Mitigation of Spent Fuel Pool in a Typical PWR

Chao Guo, Zhenzhen Ge, Feiye Liao, Peng Chen, Dongyu He
Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A007, August 8–12, 2022
Paper No: ICONE29-91550
https://doi.org/10.1115/ICONE29-91550
View Paper titled, Assessment on Accident and Mitigation of Spent Fuel Pool in a Typical PWR
Open the PDF for Assessment on Accident and Mitigation of Spent Fuel Pool in a Typical PWR in another window
Topics: Accidents, Pressurized water reactors, Spent nuclear fuels
Proceedings Papers

Sensitivity Analysis on Key Parameters of Severe Accident Source Term of PWR

Pingwen Ou, Yongzheng Chen, Dongyu He, Peng Chen
Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A009, August 8–12, 2022
Paper No: ICONE29-91730
https://doi.org/10.1115/ICONE29-91730
View Paper titled, Sensitivity Analysis on Key Parameters of Severe Accident Source Term of PWR
Open the PDF for Sensitivity Analysis on Key Parameters of Severe Accident Source Term of PWR in another window
Topics: Accidents, Pressurized water reactors, Sensitivity analysis
Proceedings Papers

The Research and Simulation of Beyond Design Basis Accidents in PWR Nuclear Power Plant

Guo Cheng
Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A004, August 8–12, 2022
Paper No: ICONE29-90267
https://doi.org/10.1115/ICONE29-90267
View Paper titled, The Research and Simulation of Beyond Design Basis Accidents in PWR Nuclear Power Plant
Open the PDF for The Research and Simulation of Beyond Design Basis Accidents in PWR Nuclear Power Plant in another window
Topics: Accidents, Design, Nuclear power stations, Pressurized water reactors, Simulation
Proceedings Papers

Research of the Standards Compilation of Welding Material for Carbon Steel in Pressurized Water Reactor Nuclear Power Plants

Bai Lin, Liang Xiaoru
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A024, August 8–12, 2022
Paper No: ICONE29-92165
https://doi.org/10.1115/ICONE29-92165
View Paper titled, Research of the Standards Compilation of Welding Material for Carbon Steel in Pressurized Water Reactor Nuclear Power Plants
Open the PDF for Research of the Standards Compilation of Welding Material for Carbon Steel in Pressurized Water Reactor Nuclear Power Plants in another window
Topics: Carbon steel, Nuclear power stations, Pressurized water reactors, Welding
Proceedings Papers

Study on the Application of Electromagnetic Stepping CRDM at Tilted Environment

Zhaohui Lu, Zewen Li, Jianming Zhou, Qingsong Liu
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A005, August 8–12, 2022
Paper No: ICONE29-90150
https://doi.org/10.1115/ICONE29-90150
View Paper titled, Study on the Application of Electromagnetic Stepping CRDM at Tilted Environment
Open the PDF for Study on the Application of Electromagnetic Stepping CRDM at Tilted Environment in another window
Topics: Design, Engineering prototypes, Failure, Kinematics, Polishing equipment, Pressurized water reactors, Stress, Structural design, Surface finishing, Wear
Proceedings Papers

Application and Prospect of Additive Manufacturing Technology in Nuclear Fuel Assembly Fabrication

Jie Ding, Yixiong Zheng, Chen Ye, Cong Li
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A016, August 8–12, 2022
Paper No: ICONE29-91618
https://doi.org/10.1115/ICONE29-91618
View Paper titled, Application and Prospect of Additive Manufacturing Technology in Nuclear Fuel Assembly Fabrication
Open the PDF for Application and Prospect of Additive Manufacturing Technology in Nuclear Fuel Assembly Fabrication in another window
Topics: Additive manufacturing, Design, Manufacturing, Nuclear fuels, Nuclear power stations, Pressurized water reactors
Proceedings Papers

Non-Destructive Examination of PWR Steam Generator Tube-Tube Plate Welds After Repairing Melting Damage

Yan Zhang, JianLei Zhang, Zhonghe Cheng
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A045, August 8–12, 2022
Paper No: ICONE29-92978
https://doi.org/10.1115/ICONE29-92978
View Paper titled, Non-Destructive Examination of PWR Steam Generator Tube-Tube Plate Welds After Repairing Melting Damage
Open the PDF for Non-Destructive Examination of PWR Steam Generator Tube-Tube Plate Welds After Repairing Melting Damage in another window
Topics: Boilers, Damage, Maintenance, Melting, Nondestructive evaluation, Pressurized water reactors, Welded joints
Proceedings Papers

Optimizing Material/Component Fabrication Processing for Improving Service Performance in Nuclear Power Plant Coolants

Zhanpeng Lu
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A030, August 8–12, 2022
Paper No: ICONE29-92321
https://doi.org/10.1115/ICONE29-92321
View Paper titled, Optimizing Material/Component Fabrication Processing for Improving Service Performance in Nuclear Power Plant Coolants
Open the PDF for Optimizing Material/Component Fabrication Processing for Improving Service Performance in Nuclear Power Plant Coolants in another window
Topics: Coolants, Cracking (Materials), Fracture (Process), Manufacturing, Nuclear power stations, Pressurized water reactors, Stress corrosion cracking
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
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
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
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
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
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
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

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
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

Validation of NUIT for Nuclides Composition Calculation With PWR Spent Fuel Isotropic Measurement

Kai Tan, Ruihan Li, Jian Li, Jingang Liang, Ding She
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A053, August 8–12, 2022
Paper No: ICONE29-91659
https://doi.org/10.1115/ICONE29-91659
View Paper titled, Validation of NUIT for Nuclides Composition Calculation With PWR Spent Fuel Isotropic Measurement
Open the PDF for Validation of NUIT for Nuclides Composition Calculation With PWR Spent Fuel Isotropic Measurement in another window
Topics: Nuclides, Pressurized water reactors, Spent nuclear fuels, Density, Errors, Accuracy and precision, Fuels, Heat, Isotopes, Nuclear fission
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
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