Topics: Accidents , Coolants , Nuclear reactors , Sensitivity analysis , Transients (Dynamics) , Cladding systems (Building) , Nuclear reactor accidents , Temperature , B-splines , Regression analysis

Bubble Boundary Detection Algorithm Without Model Training

Johnson Lorlornyo Abusah, Shouxu Qiao, Sichao Tan

ICONE 2022; V07AT07A007https://doi.org/10.1115/ICONE29-89045

Abstract

View Articletitled, Bubble Boundary Detection Algorithm Without Model Training

PDF

Topics: Algorithms , Artificial intelligence , Bubbles , Computers

Heat Transfer Characteristics of Two-Layer Corium Pools Under Rolling Conditions

Simin Luo, Peng Chen, Yapei Zhang, Dekui Zhan, Guanghui Su

ICONE 2022; V07AT07A008https://doi.org/10.1115/ICONE29-89069

Abstract

View Articletitled, Heat Transfer Characteristics of Two-Layer Corium Pools Under Rolling Conditions

PDF

Topics: Heat transfer

Estimation of the 1F2 Core Thermal Status During the Core Heat-Up Phase With MELCOR-2.2

Shotaro Osako, Xin Li, Akifumi Yamaji

ICONE 2022; V07AT07A009https://doi.org/10.1115/ICONE29-89102

Abstract

View Articletitled, Estimation of the 1F2 Core Thermal Status During the Core Heat-Up Phase With MELCOR-2.2

PDF

Topics: Accidents , Fuels , Fukushima nuclear disaster, Japan, 2011 , Heat , Oxidation , Melting , Temperature , Leakage , Nuclear decommissioning , Nuclear power stations

Research on Compliance Between Large Break LOCA of HPR1000 and New LOCA Acceptance Criterion 10CFR50.46c

Wang Weiwei, Yang Jiang, Lin Zhikang, Lu Xianghui, Zhang Ying, Shen Ting

ICONE 2022; V07AT07A010https://doi.org/10.1115/ICONE29-89155

Abstract

View Articletitled, Research on Compliance Between Large Break LOCA of HPR1000 and New LOCA Acceptance Criterion 10CFR50.46c

PDF

Topics: Cladding systems (Building) , Embrittlement , Fracture (Materials) , Fracture (Process) , Fuels , Hydrogen , Nuclear power stations , Oxidation , Oxygen , Safety

Numerical Study on Flow and Heat Transfer Characteristics of Supercritical Water in Tubes With Variable Inclination

Meng-Meng Liu, Zhen Zhang, Zhi-Qiang Chen, Xing-Tuan Yang

ICONE 2022; V07AT07A011https://doi.org/10.1115/ICONE29-89230

Abstract

View Articletitled, Numerical Study on Flow and Heat Transfer Characteristics of Supercritical Water in Tubes With Variable Inclination

PDF

Topics: Flow (Dynamics) , Heat transfer , Water

Study on Evaluation Method of Radial Power Reference Distribution of PWR

Ting Wei, Yu Huang, Zhidong Yue, Ying Zhang

ICONE 2022; V07AT07A012https://doi.org/10.1115/ICONE29-89360

Abstract

View Articletitled, Study on Evaluation Method of Radial Power Reference Distribution of PWR

PDF

Topics: Evaluation methods , Manufacturing , Pressurized water reactors , Safety , Accidents , Computer programming , Design , Engineers , Steam

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

ICONE 2022; V07AT07A013https://doi.org/10.1115/ICONE29-89383

Abstract

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

PDF

Topics: Accidents , Cladding systems (Building) , Coolants , Damage , Fuel rods , Heat , Pressure , Resonance ionization spectroscopy , Safety , Leakage

Research on Influence of Fuel Crud in Reactivity Initiated Accident

Liye Zang

ICONE 2022; V07AT07A014https://doi.org/10.1115/ICONE29-89385

Abstract

View Articletitled, Research on Influence of Fuel Crud in Reactivity Initiated Accident

PDF

Topics: Accidents , Cladding systems (Building) , Fuels , Temperature , Thermal conductivity

Experimental Research of Bundles Radial Power Distribution Influencing Factor on Fuel Assembly Mixing Characteristics

Cheng Cheng, Lu Donghua, Su Qianhua, Wang Chengyue, Xi Yanyan

ICONE 2022; V07AT07A015https://doi.org/10.1115/ICONE29-89433

Abstract

View Articletitled, Experimental Research of Bundles Radial Power Distribution Influencing Factor on Fuel Assembly Mixing Characteristics

PDF

Topics: Fuels , Manufacturing

Scaling of Thermal and Flow Behavior in Dry Storage Casks for Nuclear Spent Fuel

Qinglong Wen, Ting Yang, Shijia Xu, Zhengquan Wang, Bo Yuan

ICONE 2022; V07AT07A016https://doi.org/10.1115/ICONE29-89444

Abstract

View Articletitled, Scaling of Thermal and Flow Behavior in Dry Storage Casks for Nuclear Spent Fuel

PDF

Topics: Flow (Dynamics) , Spent nuclear fuels , Storage

HL1000 Nuclear Power Station Emergency Borating System Capacity Demonstration

Zhaohua Tian, Qiang Li

ICONE 2022; V07AT07A017https://doi.org/10.1115/ICONE29-89471

Abstract

View Articletitled, HL1000 Nuclear Power Station Emergency Borating System Capacity Demonstration

PDF

Topics: Design , Emergencies , Nuclear power stations

Analysis of Leakage Flow in Shell Side of Regenerative Heat Exchanger in Chemical and Volume Control System

Zili Gong, Shengzhi Yu, Zhengfei Kuang

ICONE 2022; V07AT07A018https://doi.org/10.1115/ICONE29-89486

Abstract

View Articletitled, Analysis of Leakage Flow in Shell Side of Regenerative Heat Exchanger in Chemical and Volume Control System

PDF

Topics: Control systems , Heat exchangers , Leakage flows , Shells

Prediction of Critical Heat Flux in Different Power Distribution of Nuclear Heating Reactor’s Rod Assembly

Gan Zhu, Heng Xie

ICONE 2022; V07AT07A019https://doi.org/10.1115/ICONE29-89564

Abstract

View Articletitled, Prediction of Critical Heat Flux in Different Power Distribution of Nuclear Heating Reactor’s Rod Assembly

PDF

Topics: Critical heat flux , Heating , Manufacturing

The Investigation on Geysering in Scaling Analyses of Natural Circulation

Xiangfei Meng

ICONE 2022; V07AT07A020https://doi.org/10.1115/ICONE29-89568

Abstract

View Articletitled, The Investigation on Geysering in Scaling Analyses of Natural Circulation

PDF

Topics: Boiling , Boiling water reactors , Circuits , Cycles , Delays , Design , Economics , Engineering prototypes , Flow (Dynamics) , Flow instability

Analysis and Evaluation of Performance for Enriched B₄C Absorber Used as Control Rod

Kaiyuan Wang, Xiaohan Liu, Xin Jin

ICONE 2022; V07AT07A021https://doi.org/10.1115/ICONE29-89917

Abstract

View Articletitled, Analysis and Evaluation of Performance for Enriched B<sub>4</sub>C Absorber Used as Control Rod

PDF

Topics: Absorption , Boron , Cladding systems (Building) , Corrosion resistance , Design , Fuels , Irradiation (Radiation exposure) , Manufacturing , Neutrons , Nuclear fission

SGTR Analysis of SMR Once-Through Steam Generator

Ye Zhu, Cheng Xiang, Liu Wei, Cai Zhiyun, Ren Yun

ICONE 2022; V07AT07A022https://doi.org/10.1115/ICONE29-90106

Abstract

View Articletitled, SGTR Analysis of SMR Once-Through Steam Generator

PDF

Topics: Boilers

Consideration of Human Factors in SGTR Mitigation Strategy

Miaomiao Xu, Runcheng Li, Yunyin Chen, Wenying Ji, Zhikang Lin

ICONE 2022; V07AT07A023https://doi.org/10.1115/ICONE29-90151

Abstract

View Articletitled, Consideration of Human Factors in SGTR Mitigation Strategy

PDF

Topics: Human factors , Pressurized water reactors , Safety , Design , Accidents , Boilers , Circuits , Containment , Rupture , Stress

Analysis of Thermal Stratification Effects in the Ring Headers of the Passive Residual Heat Removal System of NHR-200-II

Yiwa Geng, Xiongbin Liu

ICONE 2022; V07AT07A024https://doi.org/10.1115/ICONE29-90285

Abstract

View Articletitled, Analysis of Thermal Stratification Effects in the Ring Headers of the Passive Residual Heat Removal System of NHR-200-II

PDF

Topics: Computational fluid dynamics , Heat , Thermal stratification

Application of the Refinement Spacer Grid Model in Subchannel Analysis Code

Si Ying Dong, Ping Yang, Fujun Gan, Yuanrong Liu

ICONE 2022; V07AT07A025https://doi.org/10.1115/ICONE29-90296

Abstract

View Articletitled, Application of the Refinement Spacer Grid Model in Subchannel Analysis Code

PDF

Topics: Axial flow , Economics , Flow (Dynamics) , Fluids , Friction , Fuel rods , Momentum , Particulate matter , Pressurized water reactors , Rods

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

Xiao Ke

ICONE 2022; V07AT07A026https://doi.org/10.1115/ICONE29-90343

Abstract

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

PDF

Topics: Accidents , Steam , Safety , Licensing , Pressurized water reactors , Vessels , Boundary-value problems , China , Design , Feedback

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

Ang Li, Yuqing Chen

ICONE 2022; V07AT07A027https://doi.org/10.1115/ICONE29-90347

Abstract

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

PDF

Topics: Accidents , Flow (Dynamics) , Pressurized water reactors , Sensitivity analysis , Uncertainty

Application of Polynomial Chaos Expansion in Uncertainty Quantification of Reactor Thermal-Hydraulic Calculation

Xiaoyu Zhang, Shubiao Dong, Wei Dong

ICONE 2022; V07AT07A028https://doi.org/10.1115/ICONE29-90403

Abstract

View Articletitled, Application of Polynomial Chaos Expansion in Uncertainty Quantification of Reactor Thermal-Hydraulic Calculation

PDF

Topics: Chaos , Polynomials , Uncertainty quantification

Effect of Brownian Diffusion on Film Condensation With Non-Condensable Gas

Cheng Peng, Youya Song, Xianpin Meng

ICONE 2022; V07AT07A029https://doi.org/10.1115/ICONE29-90418

Abstract

View Articletitled, Effect of Brownian Diffusion on Film Condensation With Non-Condensable Gas

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Topics: Diffusion (Physics) , Film condensation , Hydrogen , Risk

Research of Supercritical Carbon Dioxide Thermal Power System Based on Lead-Cooled Fast Reactor

Zhihui Li, Chunyuan Liu, Mian Xing, Gang Zheng, Yu Wang

ICONE 2022; V07AT07A030https://doi.org/10.1115/ICONE29-90432

Abstract

View Articletitled, Research of Supercritical Carbon Dioxide Thermal Power System Based on Lead-Cooled Fast Reactor

PDF

Topics: Brayton cycle , Compression , Fast neutron reactors , Supercritical carbon dioxide , Thermal energy

Thermal Analysis and Optimization of the Heat Exchange System in the Test Loop for the Fuel Assembly Steady-State Irradiation Based on a Re-Evaluation Method

Si Junping, Liu Xiaosong, Zhao Wenbin, Xu Yuheng, Lei Jin, Zhang Wenlong, Huang Gang

ICONE 2022; V07AT07A031https://doi.org/10.1115/ICONE29-90468

Abstract

View Articletitled, Thermal Analysis and Optimization of the Heat Exchange System in the Test Loop for the Fuel Assembly Steady-State Irradiation Based on a Re-Evaluation Method

PDF

Topics: Fuels , Heat , High temperature , Irradiation (Radiation exposure) , Manufacturing , Optimization , Steady state , Thermal analysis , Water

Numerical Investigation on Transport Characteristics of Hydrogen-Air-Steam Mixture Induced by Condensation in the Single Compartment

Feng Liu, Zhongning Sun, Haozhi Bian, Ming Ding

ICONE 2022; V07AT07A032https://doi.org/10.1115/ICONE29-90644

Abstract

View Articletitled, Numerical Investigation on Transport Characteristics of Hydrogen-Air-Steam Mixture Induced by Condensation in the Single Compartment

PDF

Topics: Condensation , Containment , Hydrogen , Steam

Experimentally Investigating Effects of Water Quality on the Critical Heat Flux for the Downward Facing Surface

Guanhong Zhang, Junming Liang, Xiangyu Yun, Huiyong Zhang

ICONE 2022; V07AT07A033https://doi.org/10.1115/ICONE29-90658

Abstract

View Articletitled, Experimentally Investigating Effects of Water Quality on the Critical Heat Flux for the Downward Facing Surface

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Topics: Critical heat flux , Heat flux , Pool boiling , Water pollution

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

Hui Liang, Zongwen Hu, Xiaxin Cao

ICONE 2022; V07AT07A034https://doi.org/10.1115/ICONE29-90727

Abstract

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

PDF

Topics: Convection , Coolants , Evaporation , Heat exchangers , Heat transfer , Nucleate pool boiling , Shells , Steam

Experiment Investigation on Onset of Flow Instability in Upward Tube Under Low Pressure Condition

Bing Yang, Minfu Zhao, Junhan Wei

ICONE 2022; V07AT07A035https://doi.org/10.1115/ICONE29-90817

Abstract

View Articletitled, Experiment Investigation on Onset of Flow Instability in Upward Tube Under Low Pressure Condition

PDF

Topics: Flow instability , Pressure , Pressure drop , Two-phase flow , Bubbles , Cooling , Flow (Dynamics) , Fluids , Heat , Heat flux

Study on Developed Mechanism Model With R-134a CHF Experiment in Round Tubes

Change Wu, Yuxiang Zhang, Junliang Guo, Jianqiang Shan, Qifeng Lv, Changyi Chen, Xiangang Fu

ICONE 2022; V07AT07A036https://doi.org/10.1115/ICONE29-90825

Abstract

View Articletitled, Study on Developed Mechanism Model With R-134a CHF Experiment in Round Tubes

PDF

Topics: Critical heat flux

Study of Application of Automatic Cooldown/Heatup Technology on CPR1000 Nuclear Power Plant

Wang Kai, Ming Jia Zhou, Wei Zhang

ICONE 2022; V07AT07A037https://doi.org/10.1115/ICONE29-91242

Abstract

View Articletitled, Study of Application of Automatic Cooldown/Heatup Technology on CPR1000 Nuclear Power Plant

PDF

Topics: Automatic control , Control systems , Cooling , Design , Heating , Heating and cooling , Nuclear power stations , Pressure , Simulation , Temperature

Wall Friction Model to Improve the Stability of Fluid Network Simulation Under Low-Flow Conditions

Dong Shubiao, Zhang Xian, Zhang Xiaoyu, Zhuang Li, Shan Fuchang, Li Fei

ICONE 2022; V07AT07A038https://doi.org/10.1115/ICONE29-91479

Abstract

View Articletitled, Wall Friction Model to Improve the Stability of Fluid Network Simulation Under Low-Flow Conditions

PDF

Topics: Flow (Dynamics) , Fluids , Friction , Simulation , Stability

Experimental Assessment of RELAP5 for the Prediction of Passive Residual Heat Removal Capacity of the Intermediate Heat Exchange Loop

Zhanfei Qi, Yanhua Wu, Zijiang Yang, Yao Xiao, Junlong Li

ICONE 2022; V07AT07A039https://doi.org/10.1115/ICONE29-91486

Abstract

View Articletitled, Experimental Assessment of RELAP5 for the Prediction of Passive Residual Heat Removal Capacity of the Intermediate Heat Exchange Loop

PDF

Topics: Heat

Investigation on Start-Up Characteristics of Secondary Passive Residual Heat Removal System Under Rolling Condition

Ao Sun, Jie Cheng, Dongbao Zhu, Chunping Tian, Pengzheng Li

ICONE 2022; V07AT07A040https://doi.org/10.1115/ICONE29-91508

Abstract

View Articletitled, Investigation on Start-Up Characteristics of Secondary Passive Residual Heat Removal System Under Rolling Condition

PDF

Topics: Heat , Thermal stratification , Nuclear power stations , Ocean engineering , Boilers , Cooling , Design , Flow (Dynamics) , Heat exchangers , Oceans

Study on Stress Prediction Method of Explosion-Proof Electric Heater in Nuclear Power Plant

Yiwei Chen, Jiashun Ruan, Yan Wang, Qiuhong Zhou, Haitao Li

ICONE 2022; V07AT07A041https://doi.org/10.1115/ICONE29-91519

Abstract

View Articletitled, Study on Stress Prediction Method of Explosion-Proof Electric Heater in Nuclear Power Plant

PDF

Topics: Explosions , Nuclear power stations , Stress

Experimental Study of the Onset of Nucleate Boiling in Vertical Rectangular Narrow Channel With Large Aspect Ratio

Cao Chengque, Kuang Bo, Zhao Yu, Deng Jian, Ding Shuhua, Wu Dan

ICONE 2022; V07AT07A042https://doi.org/10.1115/ICONE29-91523

Abstract

View Articletitled, Experimental Study of the Onset of Nucleate Boiling in Vertical Rectangular Narrow Channel With Large Aspect Ratio

PDF

Topics: Nucleate boiling

Further Elaboration of Single Bubble Expansion Model and Analysis of Pressure Response Within Water-Glycerol System

Feng Mao, Tao Wu, Lei Zhang, Xinhai Xu, Xiangyu Yun, Donghua Lu, Huiyong Zhang

ICONE 2022; V07AT07A043https://doi.org/10.1115/ICONE29-91530

Abstract

View Articletitled, Further Elaboration of Single Bubble Expansion Model and Analysis of Pressure Response Within Water-Glycerol System

PDF

Topics: Bubbles , Convection , Heating , Pressure , Water

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

ICONE 2022; V07AT07A044https://doi.org/10.1115/ICONE29-91561

Abstract

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

PDF

Topics: Circuits , Cladding systems (Building) , Pressurized water reactors , Wear

Experimental Study on Statistical Properties of Two-Phase Flow Instability for Boiling

Yuanli Sun, Zhihao Song, Houde Song, Xiaojing Liu, Hui He

ICONE 2022; V07AT07A045https://doi.org/10.1115/ICONE29-91599

Abstract

View Articletitled, Experimental Study on Statistical Properties of Two-Phase Flow Instability for Boiling

PDF

Topics: Boiling , Flow (Dynamics) , Flow instability , Two-phase flow

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

ICONE 2022; V07AT07A046https://doi.org/10.1115/ICONE29-91604

Abstract

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

PDF

Topics: Evaluation methods , Flow (Dynamics) , Flow-induced vibrations , Fuels , Manufacturing , Pressurized water reactors

Study of Effective Isolation Technology of Main Feedwater

Jiaming Zhao, Liqiang Fang, Liang Ding

ICONE 2022; V07AT07A047https://doi.org/10.1115/ICONE29-91611

Abstract

View Articletitled, Study of Effective Isolation Technology of Main Feedwater

PDF

Topics: Feedwater , Valves , Water hammer

Effect of Quantity of Inserted Small Spheres on the Heat Transfer Characteristics of a Structured Pebble Bed

Leisheng Chen, Ruixiang Sun, Jiahao Zhao, Jaeyoung Lee

ICONE 2022; V07AT07A048https://doi.org/10.1115/ICONE29-91668

Abstract

View Articletitled, Effect of Quantity of Inserted Small Spheres on the Heat Transfer Characteristics of a Structured Pebble Bed

PDF

Topics: Heat transfer

Numerical Study on Heat Transfer Enhancement of Modified Wall in U-Tube Steam Generator in LFR

Junjie Yuan, Li Liu

ICONE 2022; V07AT07A049https://doi.org/10.1115/ICONE29-91701

Abstract

View Articletitled, Numerical Study on Heat Transfer Enhancement of Modified Wall in U-Tube Steam Generator in LFR

PDF

Topics: Boilers , Heat transfer

Fluid-Thermal-Mechanical Coupling Analysis of the Reactor Vessel of Natural Circulation Lead-Cooled Fast Reactor SNCLFR-100

Wenshun Duan, Kefan Zhang, Hongli Chen

ICONE 2022; V07AT07A050https://doi.org/10.1115/ICONE29-91709

Abstract

View Articletitled, Fluid-Thermal-Mechanical Coupling Analysis of the Reactor Vessel of Natural Circulation Lead-Cooled Fast Reactor SNCLFR-100

PDF

Topics: Fast neutron reactors , Fluids , Reactor vessels

Characteristic Behavior of Flow Field in Blocked Fuel Assembly Flow Channel under Steady Flow Condition

Mathew Jayeola, Sichao Tan, Shouxu Qiao, Ayodeji Ala, Fulgence Dione

ICONE 2022; V07AT07A051https://doi.org/10.1115/ICONE29-91739

Abstract

View Articletitled, Characteristic Behavior of Flow Field in Blocked Fuel Assembly Flow Channel under Steady Flow Condition

PDF

Topics: Flow (Dynamics) , Fuel rods , Fuels , Manufacturing , Turbulence

A Mechanistic Model for Predicting the Void Fraction in a One-Side Heated Annular Channel

He Wen, Zhao Chenru, Bo Hanliang

ICONE 2022; V07AT07A052https://doi.org/10.1115/ICONE29-91755

Abstract

View Articletitled, A Mechanistic Model for Predicting the Void Fraction in a One-Side Heated Annular Channel

PDF

Topics: Boiling , Bubbles , Flow (Dynamics) , Porosity , Subcooling

Analysis of RCCA Ejection Accident Under Extended Low Power Operation of CPR1000

Qin Zhou, Qiang Li, Ming Zhou, Liye Zang

ICONE 2022; V07AT07A053https://doi.org/10.1115/ICONE29-91790

Abstract

View Articletitled, Analysis of RCCA Ejection Accident Under Extended Low Power Operation of CPR1000

PDF

Topics: Accidents

Experimental Study of the Outlet Boron Concentration Dynamic Characteristic of the Volume Control Tank in Boration Process

Xiaowei Jin, Naihua Wang, Xiangyu Chi

ICONE 2022; V07AT07A054https://doi.org/10.1115/ICONE29-91801

Abstract

View Articletitled, Experimental Study of the Outlet Boron Concentration Dynamic Characteristic of the Volume Control Tank in Boration Process

PDF

Topics: Boron , Flow (Dynamics) , Nozzles , Water , Density , Errors , Nuclear reactor coolants

Investigation the Fuel Damage Fraction of IB-LOCA

Zhidong Yue, Ting Wei, Wei Cai, Xiao Ke, Ying Zhang

ICONE 2022; V07AT07A055https://doi.org/10.1115/ICONE29-91811

Abstract

View Articletitled, Investigation the Fuel Damage Fraction of IB-LOCA

PDF

Topics: Cladding systems (Building) , Damage , Fuels

Prediction of Critical Heat Flux Based on Random Forest Algorithm

Zhuo Sun, Mingyang Han, Peng Yuan, Lei Gong, Di Chen, Guanghui Yuan, Shuang Zhang

ICONE 2022; V07AT07A056https://doi.org/10.1115/ICONE29-91840

Abstract

View Articletitled, Prediction of Critical Heat Flux Based on Random Forest Algorithm

PDF

Topics: Algorithms , Critical heat flux

Experimental Study on Natural Circulation in Pool Type Fast Reactor Using a Water Model

Daoxi Cheng, Xuefeng Zhang, Kaiwen Du, Xiaoguang Qi, Weiming Zhai, Song Yu, Ping Zhou, Baohua Chai

ICONE 2022; V07AT07A057https://doi.org/10.1115/ICONE29-91869

Abstract

View Articletitled, Experimental Study on Natural Circulation in Pool Type Fast Reactor Using a Water Model

PDF

Topics: Fast neutron reactors , Water

An Experimental Study of the Gas-Liquid Mass Transfer in the Volume Control Tank

Qian Su, Naihua Wang, Xiangyu Chi

ICONE 2022; V07AT07A058https://doi.org/10.1115/ICONE29-91937

Abstract

View Articletitled, An Experimental Study of the Gas-Liquid Mass Transfer in the Volume Control Tank

PDF

Topics: Mass transfer

ATHENA Main Heat Exchanger Conceptual Design and Thermal-Hydraulic Assessment With RELAP5 Code

Tommaso Del Moro, Pierdomenico Lorusso, Fabio Giannetti, Mariano Tarantino, Marco Caramello, Damiano Vitale Di Maio

ICONE 2022; V07AT07A059https://doi.org/10.1115/ICONE29-91997

Abstract

View Articletitled, ATHENA Main Heat Exchanger Conceptual Design and Thermal-Hydraulic Assessment With RELAP5 Code

PDF

Topics: Conceptual design , Heat exchangers , Thermal hydraulics

Visual Experimental Investigation on Vapor-Liquid Interface Fluctuation Characteristics During CHF Transient

Haidong Liu, Deqi Chen, Jiang Qin, Peigang Yan

ICONE 2022; V07AT07A060https://doi.org/10.1115/ICONE29-92044

Abstract

View Articletitled, Visual Experimental Investigation on Vapor-Liquid Interface Fluctuation Characteristics During CHF Transient

PDF

Topics: Boiling , Critical heat flux , Flow (Dynamics) , Transients (Dynamics) , Vapors

Metastable Phase Optimization of Delayed Equilibrium Model for Critical Flow in Slit

Yuxiang He, Weiguo Gu, Dezhong Wang

ICONE 2022; V07AT07A061https://doi.org/10.1115/ICONE29-92057

Abstract

View Articletitled, Metastable Phase Optimization of Delayed Equilibrium Model for Critical Flow in Slit

PDF

Topics: Equilibrium (Physics) , Flow (Dynamics) , Optimization

Development of Quench Analysis Program Based on ARSAC

Lei Zhong, Hongxing Yu, Deqi Chen, Hanzhou Liu, Jian Deng, Dan Wu

ICONE 2022; V07AT07A062https://doi.org/10.1115/ICONE29-92080

Abstract

View Articletitled, Development of Quench Analysis Program Based on ARSAC

PDF

Topics: Boiling , China , Cladding systems (Building) , Film boiling , Fuels , Heat transfer , Nuclear reactors , Oxidation , Quenching (Metalworking) , Temperature

Heat Loss Estimation in Small Natural Circulation Loop

Zhiwei Liu, Xinguo Yu, Wenda Liu

ICONE 2022; V07AT07A063https://doi.org/10.1115/ICONE29-92094

Abstract

View Articletitled, Heat Loss Estimation in Small Natural Circulation Loop

PDF

Topics: Heat losses

Relap5 MOD3.2 Lead and LBE Model Addition and Program Validation

Sifan Dong, Xiao Luo, Hongli Chen

ICONE 2022; V07AT07A064https://doi.org/10.1115/ICONE29-92103

Abstract

View Articletitled, Relap5 MOD3.2 Lead and LBE Model Addition and Program Validation

PDF

Topics: China , Errors , Fast neutron reactors , Flow (Dynamics) , Fluids , Heat , Liquid metals , Safety , Simulation , Simulation results

Numerical Study of Pressure Wave Effect in Steam Generator Tube Rupture Accident of Lead-Cooled Fast Reactor

Chong Qin, Kefan Zhang, Wenpei Feng, Hongli Chen

ICONE 2022; V07AT07A065https://doi.org/10.1115/ICONE29-92114

Abstract

View Articletitled, Numerical Study of Pressure Wave Effect in Steam Generator Tube Rupture Accident of Lead-Cooled Fast Reactor

PDF

Topics: Accidents , Boilers , Fast neutron reactors , Pressure , Rupture , Waves

The Experimental Study on Critical Heat Flux in Vertical Eccentric Internally Heated Annuli

Junliang Guo, Huanjun Kong, Miao Gui, Yujiao Peng, Jianqiang Shan

ICONE 2022; V07AT07A066https://doi.org/10.1115/ICONE29-92115

Abstract

View Articletitled, The Experimental Study on Critical Heat Flux in Vertical Eccentric Internally Heated Annuli

PDF

Topics: Annulus , Critical heat flux

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

Bowen Yang, Jianqiang Shan, Li Ge, Kaidong Chen

ICONE 2022; V07AT07A067https://doi.org/10.1115/ICONE29-92118

Abstract

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

PDF

Topics: Accidents , Fuels , Performance evaluation , Pressurized water reactors , Safety

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

Yuchen Zhang, Yuzhou Lu, Xiangyu Yun, Huiyong Zhang

ICONE 2022; V07AT07A068https://doi.org/10.1115/ICONE29-92162

Abstract

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

PDF

Topics: Accidents , China , Containment , Erosion , Helium , Hydrogen , Nuclear power , Pressurized water reactors , Sprays , Steam

Research on the Natural Circulation Flow in Deep Pool-Type Nuclear Reactor

Gongqing Wang, Zhiting Yue, Rulei Sun, Bo Wang, Xingmin Liu, Ruifeng Tian

ICONE 2022; V07AT07A069https://doi.org/10.1115/ICONE29-92183

Abstract

View Articletitled, Research on the Natural Circulation Flow in Deep Pool-Type Nuclear Reactor

PDF

Topics: Flow (Dynamics) , Nuclear reactors

Experimental Investigation on Heat Transfer Enhance Effect of Spacer Grid in a 5×5 Rod Bundle

Chaozhu Zhang, Ping Yang, Fujun Gan, Yao Xiao, Junlong Li, Zhenxing Wang

ICONE 2022; V07AT07A070https://doi.org/10.1115/ICONE29-92187

Abstract

View Articletitled, Experimental Investigation on Heat Transfer Enhance Effect of Spacer Grid in a 5×5 Rod Bundle

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Topics: Fuel rods , Heat transfer

Simulation Study on Start-Up Strategy and Characteristics of Helical Coil Once-Through Steam Generator

Yaxin Gao, Jing Tang, Yisong Hu, Tianming Ruan

ICONE 2022; V07AT07A071https://doi.org/10.1115/ICONE29-92205

Abstract

View Articletitled, Simulation Study on Start-Up Strategy and Characteristics of Helical Coil Once-Through Steam Generator

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Topics: Boilers , Flow instability , Simulation

Data Assimilation in Sub-Channel Analysis Model Based on Ensemble Kalman Filter

Xiaoyan Yang, Hongyi Yang

ICONE 2022; V07AT07A072https://doi.org/10.1115/ICONE29-92214

Abstract

View Articletitled, Data Assimilation in Sub-Channel Analysis Model Based on Ensemble Kalman Filter

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Topics: Kalman filters , Design , Nuclear reactors , Porosity , Safety , Simulation , Transients (Dynamics)

Numerical Analysis of Fuel Rod Rib Structure Influence on Flow And Heat Transfer of Supercritical Carbon Dioxide

Dapeng Xi, Minyun Liu, Shenghui Liu, Jinguang Zang, Yanping Huang

ICONE 2022; V07AT07A073https://doi.org/10.1115/ICONE29-92224

Abstract

View Articletitled, Numerical Analysis of Fuel Rod Rib Structure Influence on Flow And Heat Transfer of Supercritical Carbon Dioxide

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Topics: Flow (Dynamics) , Fuel rods , Heat transfer , Numerical analysis , Supercritical carbon dioxide , Annulus , Heat transfer coefficients , Heating , Nuclear power , Turbulence