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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
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Topics: Fuel rods, Pressurized water reactors, Turbulence, Two-phase flow, Critical heat flux, Axial flow, Convection, Fluids, Pipes, Temperature
Proceedings Papers

Analysis and Research of Code Revision for Design of Nuclear Safety Related Concrete Structures of Pressurized Water Reactor Nuclear Power Plants in China

Jun Huang, Weiguo Zhang, Xueyuan Liang, Feifei Wu, Jing Xu, Shaolin Zhang, Wen Yang, Zhiyao Tang
Proc. ASME. ICONE29, Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues, V006T06A018, August 8–12, 2022
Paper No: ICONE29-93834
DOI: https://doi.org/10.1115/ICONE29-93834
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Topics: China, Concretes, Design, Nuclear power stations, Pressurized water reactors, Safety
Proceedings Papers

Integration and Future Development of Technical Standards for PWR Nuclear Pressure Equipment

Feifei Wu, Zhenbang Dong, Jun Huang, Shangyuan Liu
Proc. ASME. ICONE29, Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues, V006T06A017, August 8–12, 2022
Paper No: ICONE29-93746
DOI: https://doi.org/10.1115/ICONE29-93746
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Topics: Engineering standards, Pressure equipment, Pressurized water reactors
Proceedings Papers

Review on Reactor Coolant Pumps Trip Criteria After Small Break LOCA in PWR

Zhenying Jiao, Zhenying Wang, Yu Huang, Liu Liu, Taike Wang
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A017, August 8–12, 2022
Paper No: ICONE29-91395
DOI: https://doi.org/10.1115/ICONE29-91395
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Topics: Cooling, Nuclear reactor coolants, Pressurized water reactors, Pumps
Proceedings Papers

Study on High Frequency Flow Induced Vibration Mechanism and Evaluation Method of PWR Fuel Assembly Grid

Jie Ding, Chaozhu Zhang, Jingya Sun, Fujun Gan, Shuhe Gong
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A046, August 8–12, 2022
Paper No: ICONE29-91604
DOI: https://doi.org/10.1115/ICONE29-91604
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Topics: Evaluation methods, Flow (Dynamics), Flow-induced vibrations, Fuels, Manufacturing, Pressurized water reactors
Proceedings Papers

Research on Fretting Wear of Grid and Cladding Tube Under Simulated Primary Circuit Environment of Pressurized Water Reactor

Tingting Liu, Kun Li, Wenhui Ma, Yuxiang Zhang, Minli Chen, Xiaohang Wu
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A044, August 8–12, 2022
Paper No: ICONE29-91561
DOI: https://doi.org/10.1115/ICONE29-91561
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Topics: Circuits, Cladding systems (Building), Pressurized water reactors, Wear
Proceedings Papers

Performance Evaluation of Typical 3-Loop PWR With Annular Fuel Assemblies Under Typical Accidents

Bowen Yang, Jianqiang Shan, Li Ge, Kaidong Chen
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A067, August 8–12, 2022
Paper No: ICONE29-92118
DOI: https://doi.org/10.1115/ICONE29-92118
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Topics: Accidents, Fuels, Performance evaluation, Pressurized water reactors, Safety
Proceedings Papers

Application of the Refinement Spacer Grid Model in Subchannel Analysis Code

Si Ying Dong, Ping Yang, Fujun Gan, Yuanrong Liu
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A025, August 8–12, 2022
Paper No: ICONE29-90296
DOI: https://doi.org/10.1115/ICONE29-90296
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Topics: Axial flow, Economics , Flow (Dynamics), Fluids, Friction, Fuel rods, Momentum, Particulate matter, Pressurized water reactors, Rods
Proceedings Papers

Study on Evaluation Method of Radial Power Reference Distribution of PWR

Ting Wei, Yu Huang, Zhidong Yue, Ying Zhang
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A012, August 8–12, 2022
Paper No: ICONE29-89360
DOI: https://doi.org/10.1115/ICONE29-89360
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Topics: Evaluation methods, Manufacturing, Pressurized water reactors, Safety, Accidents, Computer programming, Design, Engineers, Steam
Proceedings Papers

Uncertainty and Sensitivity Analysis on Loss-of-Flow Accident for Small Integrated Pressurized Water Reactor

Ang Li, Yuqing Chen
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A027, August 8–12, 2022
Paper No: ICONE29-90347
DOI: https://doi.org/10.1115/ICONE29-90347
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Topics: Accidents, Flow (Dynamics), Pressurized water reactors, Sensitivity analysis, Uncertainty
Proceedings Papers

The Application Study of Conservative Best-Estimated Approach for Steam Line Break Accident

Xiao Ke
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A026, August 8–12, 2022
Paper No: ICONE29-90343
DOI: https://doi.org/10.1115/ICONE29-90343
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Topics: Accidents, Steam, Safety, Licensing, Pressurized water reactors, Vessels, Boundary-value problems, China, Design, Feedback
Proceedings Papers

The Investigation on Geysering in Scaling Analyses of Natural Circulation

Xiangfei Meng
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A020, August 8–12, 2022
Paper No: ICONE29-89568
DOI: https://doi.org/10.1115/ICONE29-89568
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Topics: Boiling, Boiling water reactors, Circuits, Cycles, Delays, Design, Economics , Engineering prototypes, Flow (Dynamics), Flow instability
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
Paper No: ICONE29-92431
DOI: https://doi.org/10.1115/ICONE29-92431
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Topics: Nuclear power stations, Pressurized water reactors, Safety, Accidents, Life extension, Uncertainty, China, Cladding systems (Building), Coolants, Design
Proceedings Papers

Experimental Investigation on the Formation and Break-Up of Gas Stratification in the COTHYD Facility

Yuchen Zhang, Yuzhou Lu, Xiangyu Yun, Huiyong Zhang
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A068, August 8–12, 2022
Paper No: ICONE29-92162
DOI: https://doi.org/10.1115/ICONE29-92162
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Topics: Accidents, China, Containment, Erosion, Helium, Hydrogen, Nuclear power, Pressurized water reactors, Sprays, Steam
Proceedings Papers

Consideration of Human Factors in SGTR Mitigation Strategy

Miaomiao Xu, Runcheng Li, Yunyin Chen, Wenying Ji, Zhikang Lin
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A023, August 8–12, 2022
Paper No: ICONE29-90151
DOI: https://doi.org/10.1115/ICONE29-90151
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Topics: Human factors, Pressurized water reactors, Safety, Design, Accidents, Boilers, Circuits, Containment, Rupture, Stress
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
DOI: https://doi.org/10.1115/ICONE29-92126
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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
DOI: https://doi.org/10.1115/ICONE29-93093
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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
DOI: https://doi.org/10.1115/ICONE29-91837
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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
DOI: https://doi.org/10.1115/ICONE29-91951
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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
DOI: https://doi.org/10.1115/ICONE29-93295
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Topics: Nuclear power stations, Pressurized water reactors, Statistical analysis, Design, Damage, Decision making, Errors, Event history analysis, Failure, Model development