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Proceedings Papers

Research of Probabilistic Safety Assessment of CPR1000 Considering Aging Effects

Xiaoming Zhang, Lijuan Wang
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A037, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92459
https://doi.org/10.1115/ICONE29-92459
View Paper titled, Research of Probabilistic Safety Assessment of CPR1000 Considering Aging Effects
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Topics: Failure, Probabilistic safety assessment, Risk, Accidents, Damage, Cables, China, Coolants, Nuclear power, Pipes
Proceedings Papers

Dynamic Modeling and Reactor Power Control of a Natural Circulation Pool-Type Lead-Cooled Fast Reactor

Yun Feng, Pei-Wei Sun, Xinyu Wei
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A104, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92872
https://doi.org/10.1115/ICONE29-92872
View Paper titled, Dynamic Modeling and Reactor Power Control of a Natural Circulation Pool-Type Lead-Cooled Fast Reactor
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Topics: Dynamic modeling, Fast neutron reactors, Control systems, Stress, Circuits, Design, Thermal energy, Coolants, Cooling, Flow (Dynamics)
Proceedings Papers

Flow Mixing Characteristics in Double Loop Reactor Pressure Vessel Under Accident Conditions

Guanhui Xie, Runcheng Li, Tianyi Wei, Zhikang Lin, Dongyang Li, Sichao Tan
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A010, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89228
https://doi.org/10.1115/ICONE29-89228
View Paper titled, Flow Mixing Characteristics in Double Loop Reactor Pressure Vessel Under Accident Conditions
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Topics: Accidents, Boron, Flow (Dynamics), Fluids, Reactor vessels, Water, Pressure vessels, Coolants, Safety, Fluid dynamics
Proceedings Papers

Early Mitigation Measures for High Flux Reactor Loss-of-Coolant Accidents

Zhuang Wang, Gan Zhu, Heng Xie
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A037, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91004
https://doi.org/10.1115/ICONE29-91004
View Paper titled, Early Mitigation Measures for High Flux Reactor Loss-of-Coolant Accidents
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Topics: Accidents, Coolants
Proceedings Papers

Quantitative Risk Assessment With CMMC Method on Abnormal Snowfall Incident for a Sodium-Cooled Fast Reactor

Risako Nakashima, Akari Koike, Takaaki Sakai, Norihiro Doda, Masaaki Tanaka
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A107, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93039
https://doi.org/10.1115/ICONE29-93039
View Paper titled, Quantitative Risk Assessment With CMMC Method on Abnormal Snowfall Incident for a Sodium-Cooled Fast Reactor
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Topics: Risk assessment, Sodium fast reactors, Hazards, Meteorology, Temperature, Dynamics (Mechanics), Probability, Chain, Climate change, Coolants
Proceedings Papers

Optimized Moderator Design and Analysis of a Pin-Type Supercritical Carbon Dioxide Reactor Based on RMC

Xingyu Zhao, Minyun Liu, Rongyi Cui, Shanfang Huang, Kan Wang, Chuan Lu
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A073, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92054
https://doi.org/10.1115/ICONE29-92054
View Paper titled, Optimized Moderator Design and Analysis of a Pin-Type Supercritical Carbon Dioxide Reactor Based on RMC
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Topics: Coolants, Design, Supercritical carbon dioxide, Yttrium
Proceedings Papers

Summary of Effects of Oxide Layer on Permeability Coefficient of Tritium

Ziling Zhou, Yu Wang, Jingni Guo, Feng Xie, Wenqian Li, Yanwei Wen, Bin Shan
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A039, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91275
https://doi.org/10.1115/ICONE29-91275
View Paper titled, Summary of Effects of Oxide Layer on Permeability Coefficient of Tritium
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Topics: Hydraulic conductivity, Very high temperature reactors, Fusion reactors, Hydrogen, Isotopes, Nuclear reactors, Coolants, Design, Diffusion (Physics), Engineering systems and industry applications
Proceedings Papers

Coupled OpenMC/CTF to VERA Core Physics Benchmark Problem 6

Chang Zhang, Ruixiang Wang, Hui Guo, Hanyang Gu, Yao Xiao
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A101, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92642
https://doi.org/10.1115/ICONE29-92642
View Paper titled, Coupled OpenMC/CTF to VERA Core Physics Benchmark Problem 6
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Topics: Physics, Thermal hydraulics, Fuels, Temperature, Coolants, Light water reactors, Manufacturing, Simulation, Eigenvalues, Fuel rods
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
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Topics: Accidents, Coolants, Pressurized water reactors
Proceedings Papers

Comparison of Numerical Analysis Methods of Coolant Environmental Fatigue Based on Strain Rate Control

Xuejiao Shao, Hai Xie, Yixiong Zhang, Furui Xiong, Xinjun Wang, Kaikai Shi, Mingda Yu, Xuan Huang
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A064, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93631
https://doi.org/10.1115/ICONE29-93631
View Paper titled, Comparison of Numerical Analysis Methods of Coolant Environmental Fatigue Based on Strain Rate Control
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Topics: Coolants, Fatigue, Numerical analysis, Stainless steel
Proceedings Papers

Evaluation of the Parameter Importance Changes Over Time for Nuclear Reactor Transients

Qingwen Xiong, Gongle Song, Peng Du, Tao Huang, Jian Deng
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A006, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89017
https://doi.org/10.1115/ICONE29-89017
View Paper titled, Evaluation of the Parameter Importance Changes Over Time for Nuclear Reactor Transients
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Topics: Accidents, Coolants, Nuclear reactors, Sensitivity analysis, Transients (Dynamics), Cladding systems (Building), Nuclear reactor accidents, Temperature, B-splines, Regression analysis
Proceedings Papers

Scaling and Engineering Design of Facility for Simulation of HTGR Reactor Building Response for a Break in Primary Coolant Break

Shripad T. Revankar, Derek W. Kultgen
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A004, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-88852
https://doi.org/10.1115/ICONE29-88852
View Paper titled, Scaling and Engineering Design of Facility for Simulation of HTGR Reactor Building Response for a Break in Primary Coolant Break
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Topics: Accidents, Coolants, Design, Engineering design, Simulation, Test facilities, Very high temperature reactors
Proceedings Papers

Influence of Low Coolant Level on Shell-Side Heat Transfer Performance in a Tubular Heat Exchanger

Hui Liang, Zongwen Hu, Xiaxin Cao
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A034, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90727
https://doi.org/10.1115/ICONE29-90727
View Paper titled, Influence of Low Coolant Level on Shell-Side Heat Transfer Performance in a Tubular Heat Exchanger
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Topics: Convection, Coolants, Evaporation, Heat exchangers, Heat transfer, Nucleate pool boiling, Shells, Steam
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

Analysis of Interfacing Systems LOCA for RIS-RHR System Under Full Pressure Conditions

Guogang Bao, Changdong Lu, Weiwei Wang, Ren Liang, Zhikang Lin, Yong Ouyang
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A013, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89383
https://doi.org/10.1115/ICONE29-89383
View Paper titled, Analysis of Interfacing Systems LOCA for RIS-RHR System Under Full Pressure Conditions
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Topics: Accidents, Cladding systems (Building), Coolants, Damage, Fuel rods, Heat, Pressure, Resonance ionization spectroscopy, Safety, Leakage
Proceedings Papers

Performance Experimental Study on Siphon Breaker of CFR600

Ping Zhou, Zhenxin Ding, Xiaoguang Qi, Xuefeng Zhang, Song Yu, Xiaoyao Ma
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A027, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92812
https://doi.org/10.1115/ICONE29-92812
View Paper titled, Performance Experimental Study on Siphon Breaker of CFR600
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Topics: Circuits, Containers, Coolants, Data acquisition, Design, Flow (Dynamics), Leakage, Pipes, Risk, Safety
Proceedings Papers

Data Driven Methods for Break Size and Location Estimation in LOCA Based on Deep Learning

Peng Yuan, Jian Deng, Zhifang Qiu, Qinglan Xu, Dahuan Zhu, Tao Huang, Zhongchun Li, Peng Du
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A006, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92380
https://doi.org/10.1115/ICONE29-92380
View Paper titled, Data Driven Methods for Break Size and Location Estimation in LOCA Based on Deep Learning
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Topics: Accidents, Algorithms, Artificial neural networks, China, Coolants, Design, Flow (Dynamics), Machine learning, Nuclear power stations, Nuclear reactors
Proceedings Papers

A Digital Proof of Concept (POC) for Simulating the Coupled Phenomena Between Neutronics, Structural and Fluid Dynamics in a Reactor Core

Jie Liu, Chunyu Zhang, Zhihao Zheng, Jiesheng Min
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A073, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93008
https://doi.org/10.1115/ICONE29-93008
View Paper titled, A Digital Proof of Concept (POC) for Simulating the Coupled Phenomena Between Neutronics, Structural and Fluid Dynamics in a Reactor Core
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Topics: Fluid dynamics, Physics, Simulation, Computational fluid dynamics, Structural analysis, American Petroleum Institute, Computation, Computer simulation, Computer software, Computer-aided engineering
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

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