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2021 28th International Conference on Nuclear Engineering

August 4–6, 2021

Virtual, Online

Conference Sponsors:

ISBN:

978-0-7918-8524-6

In This Volume

Front Matter (1)
Operating Plant Challenges, Successes, and Lessons Learned (7)
Nuclear Plant Engineering (35)
Advanced Reactors and Fusion (9)
Small Modular and Micro-Reactors Technologies and Applications (18)

Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications

Front Matter

ICONE28 Front Matter

ICONE 2021; V001T00A001https://doi.org/10.1115/ICONE28-FM1

Abstract

View Articletitled, ICONE28 Front Matter

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Operating Plant Challenges, Successes, and Lessons Learned

Research on Setting Alarm Thresholds of Gaseous Effluent Radiation Monitoring From Nuclear Power Plants in China

Wei He, Jing Jiang, Chen Xu, Qiang Lei, Chunyan Xu, Xinhua Liu, Yu Wang, Feng Xie

ICONE 2021; V001T01A001https://doi.org/10.1115/ICONE28-62558

Abstract

View Articletitled, Research on Setting Alarm Thresholds of Gaseous Effluent Radiation Monitoring From Nuclear Power Plants in China

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Topics: China , Nuclear power stations , Radiation measurement

Development of Digital Twins of PWR Steam Generators: Description of Two Maintenance-Oriented Use Cases

Enrico Deri, Christophe Varé, Matthieu Wintergerst

ICONE 2021; V001T01A002https://doi.org/10.1115/ICONE28-63246

Abstract

View Articletitled, Development of Digital Twins of PWR Steam Generators: Description of Two Maintenance-Oriented Use Cases

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Topics: Boilers , Maintenance , Pressurized water reactors , Computation , Design , Emergency preparedness , Engineering disciplines , Fracture (Materials) , Inspection , Instrumentation

Key Element Analysis and Suggestion for Strengthen the Quality Management of Nuclear Power Plant Fasteners

Yan Lu, Ligong Ling, Yu Xu, Chen Gao

ICONE 2021; V001T01A003https://doi.org/10.1115/ICONE28-64142

Abstract

View Articletitled, Key Element Analysis and Suggestion for Strengthen the Quality Management of Nuclear Power Plant Fasteners

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Topics: Fasteners , Inspection , Nuclear industry , Nuclear power stations , Quality control , Quality management

Apros-Based Loviisa NPP Full Scope Training Simulator and Engineering Model

Arttu Meriläinen, Olli Viljakainen, Karri Honkoila, Ari Lahtela

ICONE 2021; V001T01A004https://doi.org/10.1115/ICONE28-64294

Abstract

View Articletitled, Apros-Based Loviisa NPP Full Scope Training Simulator and Engineering Model

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Topics: Engineering models , Nuclear power stations , Accidents , Circuits , Accident management , Computer software , Containment , Design , Diesel generators , Electronic systems

A Sodium-Cooled Fast Reactor Simulation System and its Application In Teaching Research Based on VPOWER Platform

Chengzhi Ji, Biheng Xie, Xiaoyu Guo, Wenbin Han, Yisheng Hao, Junyi Chen, Shanfang Huang, Kan Wang, Hongbin Wei, Yanming Liang

ICONE 2021; V001T01A005https://doi.org/10.1115/ICONE28-64364

Abstract

View Articletitled, A Sodium-Cooled Fast Reactor Simulation System and its Application In Teaching Research Based on VPOWER Platform

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Topics: Simulation , Sodium fast reactors , Teaching

Experimental Study on Performance Improvement of HTR-10 Helium Purification System

Fangfang Wang, Liqiang Wei, Tianyu Kang, Chuangguo Hu, Feng Xie, Xiaoming Chen, Lei Shi

ICONE 2021; V001T01A006https://doi.org/10.1115/ICONE28-64681

Abstract

View Articletitled, Experimental Study on Performance Improvement of HTR-10 Helium Purification System

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Topics: Copper , Helium , Particulate matter , Circuits , Desorption , Electron microscopes , Feedback , Flow (Dynamics) , High temperature , Service life (Equipment)

Automated Eddy Current Array Sensor Delivery Tool for Nondestructive Examination of Spent Fuel Pool Liner

Michael Smith, Emily Abbate, Joey Phillips, Byungsik Yoon

ICONE 2021; V001T01A007https://doi.org/10.1115/ICONE28-65628

Abstract

View Articletitled, Automated Eddy Current Array Sensor Delivery Tool for Nondestructive Examination of Spent Fuel Pool Liner

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Topics: Eddies (Fluid dynamics) , Eddy currents (Electricity) , Inspection , Nondestructive evaluation , Sensors , Spent nuclear fuels

Nuclear Plant Engineering

Outline of Guideline for Seismic Response Analysis Method Using 3D Finite Element Model of Reactor Building

Byunghyun Choi, Akemi Nishida, Tadahiko Shiomi, Manabu Kawata, Yinsheng Li

ICONE 2021; V001T02A001https://doi.org/10.1115/ICONE28-61786

Abstract

View Articletitled, Outline of Guideline for Seismic Response Analysis Method Using 3D Finite Element Model of Reactor Building

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Topics: Finite element model

Study on the Transport Mechanism and Troubleshooting Analysis of Spherical Fuel in High Temperature Gas Cooled Reactor

Jinhua Wang, Yuchen Hao, Yue Li, Bin Wu, Haitao Wang, Tao Ma

ICONE 2021; V001T02A002https://doi.org/10.1115/ICONE28-63134

Abstract

View Articletitled, Study on the Transport Mechanism and Troubleshooting Analysis of Spherical Fuel in High Temperature Gas Cooled Reactor

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Topics: Fuels , Gas cooled reactors , High temperature , Nuclear power , Transportation systems

Application for 3D Laser Scanning During Construction Stage of Nuclear Power Project

Wei-ting He, Wei-feng Jiang, Yi-Kun Zhou

ICONE 2021; V001T02A003https://doi.org/10.1115/ICONE28-63294

Abstract

View Articletitled, Application for 3D Laser Scanning During Construction Stage of Nuclear Power Project

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Topics: Construction , Design , Lasers , Nuclear power

Study on Dehumidification of Carbon Materials Based on Thermogravimetry

Da Yan, Kaiyue Shen, Yicheng Guo, Huaqiang Yin, Xuedong He, Tao Ma

ICONE 2021; V001T02A004https://doi.org/10.1115/ICONE28-63633

Abstract

View Articletitled, Study on Dehumidification of Carbon Materials Based on Thermogravimetry

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Topics: Carbon , Dehumidification , Thermogravimetry , Very high temperature reactors , Temperature , Boron , Graphite , High temperature , Corrosion , Desorption

Oxidation Behaviors of the High Temperature Alloys in the Impure Helium and Argon

Wei Zheng, Haoxiang Li, Qiuhao Wang, Huaqiang Yin, Xuedong He, Hua Fan, Tao Ma

ICONE 2021; V001T02A005https://doi.org/10.1115/ICONE28-63659

Abstract

View Articletitled, Oxidation Behaviors of the High Temperature Alloys in the Impure Helium and Argon

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Topics: Alloys , Corrosion , Helium , High temperature , Oxidation , Very high temperature reactors

Research on Nuclear Turbine Control and Protection System Based on DCS Integrated Technical Solution

Guilian Shi, Jikun Wang, Jingbin Gao

ICONE 2021; V001T02A006https://doi.org/10.1115/ICONE28-64191

Abstract

View Articletitled, Research on Nuclear Turbine Control and Protection System Based on DCS Integrated Technical Solution

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Topics: Nuclear power stations , Security , Turbines , Control systems , Safety , China , Cycles , Engineering prototypes , Maintenance , Steam turbines

Analysis of Flow Resistance Influence on Step-Down Process of the Control Rod Hydraulic Drive System

Linqing Yang, Benke Qin, Hanliang Bo

ICONE 2021; V001T02A007https://doi.org/10.1115/ICONE28-64227

Abstract

View Articletitled, Analysis of Flow Resistance Influence on Step-Down Process of the Control Rod Hydraulic Drive System

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Topics: Flow (Dynamics) , Hydraulic cylinders , Hydraulic drive systems , Valves

Affect Analysis of Surface Liquid Film Coverage on the Safety Performance of Containment

Xingwei Shi, Zhuang Shaoxin, Cui Xinfang, Song Wei, Zuo Jiaxu

ICONE 2021; V001T02A008https://doi.org/10.1115/ICONE28-64278

Abstract

View Articletitled, Affect Analysis of Surface Liquid Film Coverage on the Safety Performance of Containment

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Topics: Containment , Liquid films , Safety , Scram , Steam

Assessment of Seismic Fragility Using a Three-Dimensional Structural Model of a Reactor Building

Akemi Nishida, Byunghyun Choi, Tadahiko Shiomi, Manabu Kawata, Yinsheng Li

ICONE 2021; V001T02A009https://doi.org/10.1115/ICONE28-64300

Abstract

View Articletitled, Assessment of Seismic Fragility Using a Three-Dimensional Structural Model of a Reactor Building

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Topics: Damage , Design , Earthquakes , Evaluation methods , Failure mechanisms , Hazards , Probabilistic risk assessment , Probability , Regulations , Safety

Estimation of Vibration Characteristics of Nuclear Facilities Based on Seismic Observation Records

Kouki Yamakawa, Masaaki Saruta, Hiroshi Moritani, Hiroaki Yamazaki, Akemi Nishida, Manabu Kawata, Kazuhiko Iigaki

ICONE 2021; V001T02A010https://doi.org/10.1115/ICONE28-64337

Abstract

View Articletitled, Estimation of Vibration Characteristics of Nuclear Facilities Based on Seismic Observation Records

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Topics: Nuclear power stations , Vibration , Displacement , Earthquakes , Excitation , Finite element model , Deformation , Pacific Ocean , Shorelines

Corrosion Behavior of Superalloys in High Temperature Gas Cooled Reactor in Impure Helium With Corrosion Time

Haoxiang Li, Bin Du, Wei Zheng, Qiuhao Wang, Huaqiang Yin, Xuedong He, Hua Fan, Tao Ma

ICONE 2021; V001T02A011https://doi.org/10.1115/ICONE28-64351

Abstract

View Articletitled, Corrosion Behavior of Superalloys in High Temperature Gas Cooled Reactor in Impure Helium With Corrosion Time

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Topics: Corrosion , Gas cooled reactors , Helium , High temperature , Oxidation , Superalloys

Optimization of Active Magnetic Bearings’ Power Supply System for Main Helium Fan in High Temperature Gas-Cooled Reactor

Huan Luo, Zhengang Shi, Yan Zhou, Ni Mo

ICONE 2021; V001T02A012https://doi.org/10.1115/ICONE28-64397

Abstract

View Articletitled, Optimization of Active Magnetic Bearings’ Power Supply System for Main Helium Fan in High Temperature Gas-Cooled Reactor

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Topics: Helium , Magnetic bearings , Optimization , Very high temperature reactors

Design and Analysis of a Reliable Communication System in Nuclear Safety Instrument & Control System

Le Li, Zhihui Zhang, Chao Gao, Fei Zhou, Guangqiang Ma

ICONE 2021; V001T02A013https://doi.org/10.1115/ICONE28-64398

Abstract

View Articletitled, Design and Analysis of a Reliable Communication System in Nuclear Safety Instrument & Control System

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Topics: Control systems , Design , Instrumentation , Nuclear power stations , Safety

Research on Multi-Objective Optimal Design of Plate Heat Exchanger in Nuclear Power Plant Cold Chain System

Weiguang Zhao, Xiuan Zhou, Jiangwu Shi, Changqi Yan, Jianjun Wang

ICONE 2021; V001T02A014https://doi.org/10.1115/ICONE28-64427

Abstract

View Articletitled, Research on Multi-Objective Optimal Design of Plate Heat Exchanger in Nuclear Power Plant Cold Chain System

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Topics: Chain , Design , Genetic algorithms , Heat exchangers , Nuclear power stations

Research on Electric and I&C Equipment Safety Function Classification of Nuclear Power Plant

Wang Yuqi, Sun Qian

ICONE 2021; V001T02A015https://doi.org/10.1115/ICONE28-64446

Abstract

View Articletitled, Research on Electric and I&C Equipment Safety Function Classification of Nuclear Power Plant

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Topics: Equipment performance , Nuclear power stations , Safety

Dynamic Characteristics Analysis of NuScale in Frequency Domain

Jingrui Yang, Qian Ma, Lingtong Han, Peiwei Sun

ICONE 2021; V001T02A016https://doi.org/10.1115/ICONE28-64460

Abstract

View Articletitled, Dynamic Characteristics Analysis of NuScale in Frequency Domain

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Topics: Boilers , Coolants , Design , Electric power generation , Feedwater , Flow (Dynamics) , Frequency-domain analysis , Heating , Momentum , Neutrons

Conceptual Design of Nuclear Wet Steam Turbines for Ease of Mass Manufacture

Edmund Ireland

ICONE 2021; V001T02A017https://doi.org/10.1115/ICONE28-64473

Abstract

View Articletitled, Conceptual Design of Nuclear Wet Steam Turbines for Ease of Mass Manufacture

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Topics: Conceptual design , Steam turbines , Construction , Design , Electric power generation , Electronics , Heat exchangers , Manufacturing

Experimental and Analytical Investigation on Local Damage To Reinforced Concrete Panels Subjected to Projectile Impact Part 1: Penetration Damage Mode due to Normal Impact

Zuoyi Kang, Yukihiko Okuda, Akemi Nishida, Haruji Tsubota, Yinsheng Li

ICONE 2021; V001T02A018https://doi.org/10.1115/ICONE28-64521

Abstract

View Articletitled, Experimental and Analytical Investigation on Local Damage To Reinforced Concrete Panels Subjected to Projectile Impact Part 1: Penetration Damage Mode due to Normal Impact

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Topics: Damage , Projectiles , Reinforced concrete

Simulation for Predicting Condition of Plant Equipment

Shoichi Kashiwase, Kenji Osaki, Makoto Hatakeyama, Tomokazu Kaneko

ICONE 2021; V001T02A019https://doi.org/10.1115/ICONE28-64527

Abstract

View Articletitled, Simulation for Predicting Condition of Plant Equipment

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Topics: Engines , Motors , Pumps , Simulation , Valves

A High-Temperature Gas-Cooled Reactor Simulation System and Its Application Based on VPOWER Platform

Biheng Xie, Chengzhi Ji, Xiaoyu Guo, Wenbin Han, Yisheng Hao, Junyi Chen, Shanfang Huang, Kan Wang, Hongbin Wei, Yanming Liang

ICONE 2021; V001T02A020https://doi.org/10.1115/ICONE28-64532

Abstract

View Articletitled, A High-Temperature Gas-Cooled Reactor Simulation System and Its Application Based on VPOWER Platform

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Topics: Simulation , Teaching , Very high temperature reactors , Accidents , Nuclear engineering , Nuclear industry , Students , Boilers , Control systems , Design

Cause Analysis and Influence Evaluation of Cracks in Thick Slab Construction

Yi Guixiang, Li Liang

ICONE 2021; V001T02A021https://doi.org/10.1115/ICONE28-64548

Abstract

View Articletitled, Cause Analysis and Influence Evaluation of Cracks in Thick Slab Construction

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Topics: Construction , Fracture (Materials) , Slabs

Research on Earthquake Acceleration Alarm of Nuclear Power Plant

Li Liang, Pan Rong, Ren Guopeng, Zhu Xiuyun

ICONE 2021; V001T02A022https://doi.org/10.1115/ICONE28-64554

Abstract

View Articletitled, Research on Earthquake Acceleration Alarm of Nuclear Power Plant

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Topics: Earthquakes , Instrumentation , Nuclear power stations

Hybrid Dynamic Response Test Focusing on the Support Structure of Piping Systems

Yukihiko Okuda, Akemi Nishida, Michiya Sakai, Yuzo Shiogama, Yinsheng Li

ICONE 2021; V001T02A023https://doi.org/10.1115/ICONE28-64586

Abstract

View Articletitled, Hybrid Dynamic Response Test Focusing on the Support Structure of Piping Systems

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Topics: Dynamic response , Piping systems , Pipes , Evaluation methods , Design , Mechanical behavior , Nuclear power stations , Probabilistic risk assessment , Structures

Research and Application of Different Seismic Analysis Methods in Nuclear Power Equipment

Xuan Huang, Furui Xiong, Shuai Liu, Huanhuan Qi, Qian Huang, Ke Zhang

ICONE 2021; V001T02A024https://doi.org/10.1115/ICONE28-64605

Abstract

View Articletitled, Research and Application of Different Seismic Analysis Methods in Nuclear Power Equipment

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Topics: Nuclear power , Seismic analysis

Improvement of Transverse Leakage Term Based on Fourier Series Expansion in the 2-D/1-D Method

Kaijie Zhu, Boran Kong, Jie Hou, Han Zhang, Jiong Guo, Fu Li

ICONE 2021; V001T02A025https://doi.org/10.1115/ICONE28-64612

Abstract

View Articletitled, Improvement of Transverse Leakage Term Based on Fourier Series Expansion in the 2-D/1-D Method

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Topics: Fourier series , Leakage

Recent Activities and New Challenges for the EUR Organization

Vincent Sorel

ICONE 2021; V001T02A026https://doi.org/10.1115/ICONE28-64617

Abstract

View Articletitled, Recent Activities and New Challenges for the EUR Organization

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Topics: Accidents , Design , Engineering standards , Fukushima nuclear disaster, Japan, 2011 , Light water reactors , Nuclear power stations , Safety , Small modular reactors

100-Gigawatt-Hour Crushed-Rock Heat Storage for Variable Electricity and Heat With Base-Load Reactor Operations

Charles Forsberg

ICONE 2021; V001T02A027https://doi.org/10.1115/ICONE28-64632

Abstract

View Articletitled, 100-Gigawatt-Hour Crushed-Rock Heat Storage for Variable Electricity and Heat With Base-Load Reactor Operations

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Topics: Heat , Heat storage , Rocks , Stress , Storage , Fluids , Heat transfer , Plasma spraying , Spraying (Coating processes) , Dimensions

Nuclear Air-Brayton Combined Cycles Using Electrically-Heated Conductive Firebrick Heat Storage and Hydrogen for Peak Power

Charles Forsberg, Daniel Stack, Patrick McDaniel

ICONE 2021; V001T02A028https://doi.org/10.1115/ICONE28-64638

Abstract

View Articletitled, Nuclear Air-Brayton Combined Cycles Using Electrically-Heated Conductive Firebrick Heat Storage and Hydrogen for Peak Power

PDF

Topics: Combined cycles , Heat storage , Hydrogen , Heat , Compressed air , High temperature , Combined cycle gas turbines , Carbon , Cycles , Energy storage

Research on Start-Up Design of Nuclear Safety Level Parallel Redundant Control Station

Guilian Shi, Yunxu Shou, Gang Li

ICONE 2021; V001T02A029https://doi.org/10.1115/ICONE28-64714

Abstract

View Articletitled, Research on Start-Up Design of Nuclear Safety Level Parallel Redundant Control Station

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Topics: Design , Safety

Research on DTS Analysis Method for 1000MWe PWR NPP

Yubin Zhang

ICONE 2021; V001T02A030https://doi.org/10.1115/ICONE28-64716

Abstract

View Articletitled, Research on DTS Analysis Method for 1000MWe PWR NPP

PDF

Topics: Nuclear power stations , Pressurized water reactors

Comparative Study on Thermal Stress Analysis and Fatigue Curve in Stress and Fatigue Calculation of Nuclear Equipment

Xuejiao Shao, Hai Xie, Yixiong Zhang, Liping Zhang, Xiaolong Fu, Xue Mi, Hui Li

ICONE 2021; V001T02A031https://doi.org/10.1115/ICONE28-64784

Abstract

View Articletitled, Comparative Study on Thermal Stress Analysis and Fatigue Curve in Stress and Fatigue Calculation of Nuclear Equipment

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Topics: Design , Fatigue , Stress , Thermal stresses

Evaluations of TiO₂ Deposition on Structure Surfaces and Water Radiolysis for the Corrosive Environment in a Reactor Pressure Vessel

Takashi Mawatari, Yasushi Yamamoto, Osamu Shibasaki, Takahiro Hara, Yusuke Horayama, Junichi Takagi

ICONE 2021; V001T02A032https://doi.org/10.1115/ICONE28-64931

Abstract

View Articletitled, Evaluations of TiO<sub>2</sub> Deposition on Structure Surfaces and Water Radiolysis for the Corrosive Environment in a Reactor Pressure Vessel

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Topics: Electrolytic corrosion , Reactor vessels , Stress corrosion cracking , Titanium dioxide , Water

Application of Combining 3D Model and Survey on Site to Simulate Dome Lifting

Wei-ting He, Yuan-xia Zhou, Jie Yang

ICONE 2021; V001T02A033https://doi.org/10.1115/ICONE28-65502

Abstract

View Articletitled, Application of Combining 3D Model and Survey on Site to Simulate Dome Lifting

PDF

Topics: Domes (Structural elements) , Plasma desorption mass spectrometry , Three-dimensional models

Experimental Simulation of Transitions Between Forced Circulation and Natural Circulation With Nuclear Reactivity Feedback

Hanying Chen, Linzhong Xia, Puzhen Gao, Sichao Tan, Hongsheng Yuan

ICONE 2021; V001T02A034https://doi.org/10.1115/ICONE28-66338

Abstract

View Articletitled, Experimental Simulation of Transitions Between Forced Circulation and Natural Circulation With Nuclear Reactivity Feedback

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Topics: Feedback , Simulation

Machine Learned Metamodeling of a Computationally Intensive Accident Simulation Code

Landon Conner, Clarence L. Worrell, James P. Spring, Jun Liao

ICONE 2021; V001T02A035https://doi.org/10.1115/ICONE28-66619

Abstract

View Articletitled, Machine Learned Metamodeling of a Computationally Intensive Accident Simulation Code

PDF

Topics: Accidents , Machinery , Metamodeling , Simulation , Artificial neural networks , Machine learning , Manufacturing , Nuclear industry , Optimization , Safety

Advanced Reactors and Fusion

Alternative Absorber Materials for Control Rods in ALFRED

Hui Guo, Xin Jin, Kuaiyuan Feng, Hanyang Gu

ICONE 2021; V001T03A001https://doi.org/10.1115/ICONE28-61123

Abstract

View Articletitled, Alternative Absorber Materials for Control Rods in ALFRED

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Topics: Fast neutron reactors , Rods

Corrosion Behavior of Iron-Chrome Alloys in Liquid Bismuth

Toshihide Takai, Tomohiro Furukawa, Shigeki Watanabe, Noriko S. Ishioka

ICONE 2021; V001T03A002https://doi.org/10.1115/ICONE28-63277

Abstract

View Articletitled, Corrosion Behavior of Iron-Chrome Alloys in Liquid Bismuth

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Topics: Alloys , Corrosion , Corrosion resistance , Iron , Oxygen , Stainless steel , Cancer , Fast neutron reactors , Irradiation (Radiation exposure) , Mass production

Numerical Investigation of Safety System Parameters in Molten Salt Reactor: Wall Effect on Freeze Valve Opening Time

Muhammad Ilham, Indarta Kuncoro Aji, Tomio Okawa

ICONE 2021; V001T03A003https://doi.org/10.1115/ICONE28-64134

Abstract

View Articletitled, Numerical Investigation of Safety System Parameters in Molten Salt Reactor: Wall Effect on Freeze Valve Opening Time

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Topics: Melting , Molten salt reactors , Safety , Solidification , Valves

A Preliminary Study on Neutronic Performance of the Spallation Target With the Proton Beam Variation

Junjie Zhou, Qin Zeng, Jinchen Yang, Yi Yang, Ying Shi, Yanyi Jiang

ICONE 2021; V001T03A004https://doi.org/10.1115/ICONE28-64388

Abstract

View Articletitled, A Preliminary Study on Neutronic Performance of the Spallation Target With the Proton Beam Variation

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Topics: Neutron flux , Proton beams , Spallation (Nuclear physics)

Numerical Study on Multiscale Heat Conduction Problems in Very High Temperature Reactor Fuel Pebble Based on OpenFOAM

Jincheng Wang, Ming Ding

ICONE 2021; V001T03A005https://doi.org/10.1115/ICONE28-64416

Abstract

View Articletitled, Numerical Study on Multiscale Heat Conduction Problems in Very High Temperature Reactor Fuel Pebble Based on OpenFOAM

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Topics: Fuels , Heat conduction , Very high temperature reactors

Sensitivity Analysis of Power Related Parameters in a Reactivity-Initiated Accident of a Molten Salt Reactor

Chaoqun Wang, Qun Yang, Kai Wang, Xiaowei Jiao, Yanhua Wu, Zhaozhong He

ICONE 2021; V001T03A006https://doi.org/10.1115/ICONE28-64430

Abstract

View Articletitled, Sensitivity Analysis of Power Related Parameters in a Reactivity-Initiated Accident of a Molten Salt Reactor

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Topics: Accidents , Molten salt reactors , Sensitivity analysis

ARKADIA – for the Innovation of Advanced Nuclear Reactor Design

Hiroyuki Ohshima, Tai Asayama, Tomohiro Furukawa, Masaaki Tanaka, Takashi Takata, Yasuhiro Enuma

ICONE 2021; V001T03A007https://doi.org/10.1115/ICONE28-64525

Abstract

View Articletitled, ARKADIA – for the Innovation of Advanced Nuclear Reactor Design

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Topics: Artificial intelligence , Computer simulation , Innovation , Nuclear design , Nuclear reactors , Optimization , Design , Safety , Carbon , Coolants

Conceptual Study of Neutron Physics of Nuclear Fuel Cycle for Ceramic Fast Reactor

Xuesong Yan, Yaling Zhang, Yucui Gao, Lei Yang

ICONE 2021; V001T03A008https://doi.org/10.1115/ICONE28-65406

Abstract

View Articletitled, Conceptual Study of Neutron Physics of Nuclear Fuel Cycle for Ceramic Fast Reactor

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Topics: Ceramics , Fast neutron reactors , High temperature , Neutrons , Nuclear fuel cycle , Physics , Spent nuclear fuels

Activities of the GIF Safety and Operation Project of Sodium-Cooled Fast Reactor Systems

Hidemasa Yamano, Marie-Sophie Chenaud, Seok-Hun Kang, Tyler Sumner, Haileyesus Tsige-Tamirat, Jin Wang, Evgeny Rozhikhin

ICONE 2021; V001T03A009https://doi.org/10.1115/ICONE28-66385

Abstract

View Articletitled, Activities of the GIF Safety and Operation Project of Sodium-Cooled Fast Reactor Systems

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Topics: Safety , Sodium fast reactors

Small Modular and Micro-Reactors Technologies and Applications

Application of EEMD-Multiscale Entropy Algorithm in the Signal Analysis of Narrow Channel Two-Phase Flow Under Rolling Motion

Wenjun Chu, Yang Liu, Hongye Zhu, Xingtuan Yang, Liqiang Pan

ICONE 2021; V001T04A001https://doi.org/10.1115/ICONE28-62494

Abstract

View Articletitled, Application of EEMD-Multiscale Entropy Algorithm in the Signal Analysis of Narrow Channel Two-Phase Flow Under Rolling Motion

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Topics: Algorithms , Entropy , Signals , Two-phase flow

Preliminary Transient Analysis for LBE-Cooled Fast Reactor BLESS-D

Mian Xing, Linsen Li, Gang Zheng, Junlang Wen, Chunyuan Liu, Yeoh Eing Yee, Zhen Luo, Peidong Sun, Jinjun Feng

ICONE 2021; V001T04A002https://doi.org/10.1115/ICONE28-63220

Abstract

View Articletitled, Preliminary Transient Analysis for LBE-Cooled Fast Reactor BLESS-D

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Topics: Fast neutron reactors , Safety , Transient analysis , Transients (Dynamics) , Design , Reactor vessels , Accidents , Boilers , Conceptual design , Coolants

Study on the Small Pressurized Water Reactor Based on Fully Ceramic Microencapsulated Fuel

Jin Feng Huang

ICONE 2021; V001T04A003https://doi.org/10.1115/ICONE28-63314

Abstract

View Articletitled, Study on the Small Pressurized Water Reactor Based on Fully Ceramic Microencapsulated Fuel

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Topics: Ceramics , Fuels , Pressurized water reactors , Cladding systems (Building) , Cycles , Nuclear power stations , Silicon , Temperature , Thermal conductivity , Boron

Progress and Prospects of Some Key Technologies for Space Nuclear Reactor

Nailiang Zhuang, Chenhao Yang, Yiqi Zhao, Yongnian Song, Xiaobin Tang

ICONE 2021; V001T04A004https://doi.org/10.1115/ICONE28-63357

Abstract

View Articletitled, Progress and Prospects of Some Key Technologies for Space Nuclear Reactor

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Topics: Nuclear reactors

Design Study of SMR Class Super FR Core for In-Vessel Retention

Ryotaro Sasaki, Akifumi Yamaji, Kyota Uchimura

ICONE 2021; V001T04A005https://doi.org/10.1115/ICONE28-64162

Abstract

View Articletitled, Design Study of SMR Class Super FR Core for In-Vessel Retention

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Topics: Accidents , Design , Small modular reactors , Supercritical water reactors , Vessels , Water

A Finnish District Heating Reactor: Thermal-Hydraulic Design and Transient Analyses

Rebekka Komu, Seppo Hillberg, Ville Hovi, Jaakko Leppänen, Joona Leskinen

ICONE 2021; V001T04A006https://doi.org/10.1115/ICONE28-64163

Abstract

View Articletitled, A Finnish District Heating Reactor: Thermal-Hydraulic Design and Transient Analyses

PDF

Topics: Central heating , Design , Heat , Transient analysis , Transients (Dynamics)

Thermal Hydraulics Analysis of a High-Performance Once-Through Steam Generator With Annular Narrow Slot Tube

Jinyu Han, Wen He, Shunran Guan, Chenru Zhao, Hanliang Bo

ICONE 2021; V001T04A007https://doi.org/10.1115/ICONE28-64168

Abstract

View Articletitled, Thermal Hydraulics Analysis of a High-Performance Once-Through Steam Generator With Annular Narrow Slot Tube

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Topics: Boilers , Thermal hydraulics

Preliminary Core Design of the Solid Moderator Reactor for Investigation of the In-Depth Europa Ice Layer

Shuta Fukizaki, Akifumi Yamaji, Takanari Fukuda

ICONE 2021; V001T04A008https://doi.org/10.1115/ICONE28-64261

Abstract

View Articletitled, Preliminary Core Design of the Solid Moderator Reactor for Investigation of the In-Depth Europa Ice Layer

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Topics: Design , Ice

A Finnish District Heating Reactor: Background and General Overview

Jaakko Leppänen, Seppo Hillberg, Ville Hovi, Rebekka Komu, Joona Kurki, Unna Lauranto, Ahti Oinonen, Jussi Peltonen, Antti Rintala, Ville Tulkki, Riku Tuominen, Ville Valtavirta

ICONE 2021; V001T04A009https://doi.org/10.1115/ICONE28-64346

Abstract

View Articletitled, A Finnish District Heating Reactor: Background and General Overview

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Topics: Central heating , Design , Coal , Governments , Heat , Boilers , Carbon , Climate , Containment , Energy generation

A Finnish District Heating Reactor: Neutronics Design and Fuel Cycle Simulations

Jaakko Leppänen, Ville Valtavirta, Riku Tuominen, Antti Rintala, Unna Lauranto

ICONE 2021; V001T04A010https://doi.org/10.1115/ICONE28-64347

Abstract

View Articletitled, A Finnish District Heating Reactor: Neutronics Design and Fuel Cycle Simulations

PDF

Topics: Central heating , Design , Engineering simulation , Nuclear fuel cycle , Simulation , Fuels , Boron , Cycles , Heating , Operating temperature