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

High-Precision Subchannel Model for Single and Two Phase Flow in PWR Rod Bundles With Mixing Grids

Li Jiang, Jianqiang Shan
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A038, August 8–12, 2022
Paper No: ICONE29-93217
DOI: https://doi.org/10.1115/ICONE29-93217
View Paper
PDF
Topics: Fuel rods, Pressurized water reactors, Turbulence, Two-phase flow, Critical heat flux, Axial flow, Convection, Fluids, Pipes, Temperature
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
Paper No: ICONE29-93265
DOI: https://doi.org/10.1115/ICONE29-93265
View Paper
PDF
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
Paper No: ICONE29-93277
DOI: https://doi.org/10.1115/ICONE29-93277
View Paper
PDF
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
Paper No: ICONE29-92184
DOI: https://doi.org/10.1115/ICONE29-92184
View Paper
PDF
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
Paper No: ICONE29-89258
DOI: https://doi.org/10.1115/ICONE29-89258
View Paper
PDF
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
Paper No: ICONE29-92493
DOI: https://doi.org/10.1115/ICONE29-92493
View Paper
PDF
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
Paper No: ICONE29-88883
DOI: https://doi.org/10.1115/ICONE29-88883
View Paper
PDF
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
Paper No: ICONE29-89223
DOI: https://doi.org/10.1115/ICONE29-89223
View Paper
PDF
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
Paper No: ICONE29-89461
DOI: https://doi.org/10.1115/ICONE29-89461
View Paper
PDF
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
Paper No: ICONE29-93351
DOI: https://doi.org/10.1115/ICONE29-93351
View Paper
PDF
Topics: Pressurized water reactors, Safety, Spent nuclear fuels, Storage
Proceedings Papers

Analysis Method to Predict Grid-to-Rod Fretting Wear of Fuel Rod in Pressurized Water Reactors

Libing Zhu, Shufeng Zhao, Jingya Sun, Shiyin Xu, Fujun Gan, Sirui Li
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A074, August 8–12, 2022
Paper No: ICONE29-93076
DOI: https://doi.org/10.1115/ICONE29-93076
View Paper
PDF
Topics: Fuel rods, Pressurized water reactors, Wear
Proceedings Papers

Analysis of the Influence of RCCA Swelling on Rod Falling and Study on Mitigation Measures

Zhipeng Lv, Guoliang Zhang, Changzheng Li, Weichao Liu, Shaofang Lin, Lihong Nie, Zhijun Li, Anlong Zhang
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A067, August 8–12, 2022
Paper No: ICONE29-93095
DOI: https://doi.org/10.1115/ICONE29-93095
View Paper
PDF
Topics: Absorption, Cladding systems (Building), Deformation, Design, Irradiation (Radiation exposure), Neutrons, Pressurized water reactors, Rods, Safety, Shock absorbers
Proceedings Papers

Validation of NUIT for Decay Heat Predictions of PWR Spent Fuel Assemblies

Jian Li, Ruihan Li, Ding She, Jin'gang Liang, Lei Shi
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A008, August 8–12, 2022
Paper No: ICONE29-89241
DOI: https://doi.org/10.1115/ICONE29-89241
View Paper
PDF
Topics: Heat, Pressurized water reactors, Spent nuclear fuels, Fuels, Neutrons, Boiling water reactors, Collapse, Cooling, Cross section (Physics), Density
Proceedings Papers

Summary of the History of Improvement and Optimization of Fuel Management Strategies for Two 1000 MWe PWR Units

Zhou Xiaoling, Xu Zhixian, Zhao Bingquan, Li Wen, Zhong Shengdong, Gao Jinghui
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A070, August 8–12, 2022
Paper No: ICONE29-92954
DOI: https://doi.org/10.1115/ICONE29-92954
View Paper
PDF
Topics: Cycles, Fuel management, Fuels, Leakage, Optimization, Pressurized water reactors
Proceedings Papers

Calculation of Detector Response Rate Based on BEAVRS Benchmark Using PWR-Core Analysis Code CORAL

Wen Yang, Baolin Liu, Shiwei Yao, Fei Chao, Xing Li, Jinrong Qiu
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A082, August 8–12, 2022
Paper No: ICONE29-93495
DOI: https://doi.org/10.1115/ICONE29-93495
View Paper
PDF
Topics: Pressurized water reactors, Sensors
Proceedings Papers

Automation of High-Fidelity Modeling of PWR Fuel Rods and Verification

Zhang Chunyu, Wang Yang, Deng Yongjun, Song Zifan, Lu Yong
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A017, August 8–12, 2022
Paper No: ICONE29-90557
DOI: https://doi.org/10.1115/ICONE29-90557
View Paper
PDF
Topics: Finite element model, Fuel rods, Modeling, Pressurized water reactors
Proceedings Papers

Improvements on Fuel Failures Diagnosis Method for Pressurized Water Reactor Nuclear Power Plant Based on Radioactive Activities Inside the Waste Gas Treatment System

Weifeng Lyu, Runchun Guo, Wenwang Ran, Yaoyi Gao, Jun Xiong
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A072, August 8–12, 2022
Paper No: ICONE29-92996
DOI: https://doi.org/10.1115/ICONE29-92996
View Paper
PDF
Topics: Failure, Fuels, Nuclear power stations, Pressurized water reactors
Proceedings Papers

Hydrogenation of Zircaloy-4 in a Defective Fuel Pellet for Pressurized Water Reactors

Doctor Enivweru, Qingyu Wang, Abiodun Ayodeji, John Njoroge
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A021, August 8–12, 2022
Paper No: ICONE29-90736
DOI: https://doi.org/10.1115/ICONE29-90736
View Paper
PDF
Topics: Corrosion, Fuels, Hydrogen embrittlement, Pressurized water reactors, Cladding systems (Building), Hydrogen, Temperature, Accidents, Boundary-value problems, Coolants
Proceedings Papers

Study on Selection Method of Shielding Nuclides in Nuclear Reactor Based on Non-Dominated Sorting

Rui Li, Shichang Liu
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A027, August 8–12, 2022
Paper No: ICONE29-90902
DOI: https://doi.org/10.1115/ICONE29-90902
View Paper
PDF
Topics: Nuclear reactors, Nuclides, Radiation (Physics), Neutrons, Cross section (Physics), Monte Carlo methods, Photons, Absorption, Databases, Elastic scattering
Proceedings Papers

A Method to Evaluate Defect Size of Failed Fuel Rods in CGN 1000MWe PWRs

Pengtao Fu, Zhijun Li
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A063, August 8–12, 2022
Paper No: ICONE29-92788
DOI: https://doi.org/10.1115/ICONE29-92788
View Paper
PDF
Topics: Failure, Fuel rods, Fuels, Nuclear fission, Pressurized water reactors, Cladding systems (Building), Rods, Irradiation (Radiation exposure)