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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93495
https://doi.org/10.1115/ICONE29-93495
View Paper titled, Calculation of Detector Response Rate Based on BEAVRS Benchmark Using PWR-Core Analysis Code CORAL
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90557
https://doi.org/10.1115/ICONE29-90557
View Paper titled, Automation of High-Fidelity Modeling of PWR Fuel Rods and Verification
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92996
https://doi.org/10.1115/ICONE29-92996
View Paper titled, Improvements on Fuel Failures Diagnosis Method for Pressurized Water Reactor Nuclear Power Plant Based on Radioactive Activities Inside the Waste Gas Treatment System
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90736
https://doi.org/10.1115/ICONE29-90736
View Paper titled, Hydrogenation of Zircaloy-4 in a Defective Fuel Pellet for Pressurized Water Reactors
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90902
https://doi.org/10.1115/ICONE29-90902
View Paper titled, Study on Selection Method of Shielding Nuclides in Nuclear Reactor Based on Non-Dominated Sorting
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92788
https://doi.org/10.1115/ICONE29-92788
View Paper titled, A Method to Evaluate Defect Size of Failed Fuel Rods in CGN 1000MWe PWRs
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Topics: Failure, Fuel rods, Fuels, Nuclear fission, Pressurized water reactors, Cladding systems (Building), Rods, Irradiation (Radiation exposure)
Proceedings Papers

Investigation of Model-Based Anomaly Detection Method for the Full-Power Natural Circulation Small Modular Reactor NHR200-II

Canxing Huang, Huasheng Xiong, Junting Feng
Proc. ASME. ICONE29, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A014, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91509
https://doi.org/10.1115/ICONE29-91509
View Paper titled, Investigation of Model-Based Anomaly Detection Method for the Full-Power Natural Circulation Small Modular Reactor NHR200-II
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Topics: Accidents, Boilers, Control systems, Coolants, Heating, Nuclear power, Pressurized water reactors, Pumps, Radioactivity, Safety
Proceedings Papers

Potential Crud Related Margin Gains With Chromium Coated Zirconium Cladding

William A. Byers, Guoqiang Wang
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A094, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-94477
https://doi.org/10.1115/ICONE29-94477
View Paper titled, Potential Crud Related Margin Gains With Chromium Coated Zirconium Cladding
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Topics: Cladding systems (Building), Zirconium, Corrosion, Coating processes, Coatings, Fuels, Pressurized water reactors, Accidents, Boiling, Boron
Proceedings Papers

Application of Genetic Algorithm in Pressure Control of Pressurizer

Yuzhong Shan, Kunpeng Xing
Proc. ASME. ICONE29, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A026, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92661
https://doi.org/10.1115/ICONE29-92661
View Paper titled, Application of Genetic Algorithm in Pressure Control of Pressurizer
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Topics: Genetic algorithms, Pressure control, Nuclear power stations, Control equipment, Control systems, Optimization, Pressure, Pressurized water reactors, Safety, Steady state
Proceedings Papers

Neutronics Design and Modelling of a Nuscale-Based Small Modular PWR

Yanfei Qiu
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A033, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93201
https://doi.org/10.1115/ICONE29-93201
View Paper titled, Neutronics Design and Modelling of a Nuscale-Based Small Modular PWR
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Topics: Design, Modeling, Pressurized water reactors, Cycles, Fuels, Safety, Feedback, Modular construction, Neutrons, Nuclear reactors
Proceedings Papers

Assessment of Passive Cooling Capability of the Westinghouse Lead Fast Reactor Under Station Blackout Conditions

Emre Tatli, Sung Jin Lee, Jun Liao, Paolo Ferroni
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A020, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91821
https://doi.org/10.1115/ICONE29-91821
View Paper titled, Assessment of Passive Cooling Capability of the Westinghouse Lead Fast Reactor Under Station Blackout Conditions
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Topics: Cooling, Fast neutron reactors, Computational fluid dynamics, Design, Heat, Reactor vessels, Vessels, Water, Accidents, Accounting
Proceedings Papers

Light Water-Cooled High-Performance Research Reactor Physics Design and Analysis

Zihao Guo, Guang Wang, Genghua Su, Xiuan Shi
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A036, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93256
https://doi.org/10.1115/ICONE29-93256
View Paper titled, Light Water-Cooled High-Performance Research Reactor Physics Design and Analysis
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Topics: Design, Irradiation (Radiation exposure), Neutron flux, Physics, Water, Biomedicine, Isotopes, Cycles, Decontamination, Fuels
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90296
https://doi.org/10.1115/ICONE29-90296
View Paper titled, Application of the Refinement Spacer Grid Model in Subchannel Analysis Code
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89360
https://doi.org/10.1115/ICONE29-89360
View Paper titled, Study on Evaluation Method of Radial Power Reference Distribution of PWR
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90347
https://doi.org/10.1115/ICONE29-90347
View Paper titled, Uncertainty and Sensitivity Analysis on Loss-of-Flow Accident for Small Integrated Pressurized Water Reactor
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90343
https://doi.org/10.1115/ICONE29-90343
View Paper titled, The Application Study of Conservative Best-Estimated Approach for Steam Line Break Accident
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89568
https://doi.org/10.1115/ICONE29-89568
View Paper titled, The Investigation on Geysering in Scaling Analyses of Natural Circulation
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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
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
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92162
https://doi.org/10.1115/ICONE29-92162
View Paper titled, Experimental Investigation on the Formation and Break-Up of Gas Stratification in the COTHYD Facility
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90151
https://doi.org/10.1115/ICONE29-90151
View Paper titled, Consideration of Human Factors in SGTR Mitigation Strategy
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Topics: Human factors, Pressurized water reactors, Safety, Design, Accidents, Boilers, Circuits, Containment, Rupture, Stress