Topics: Accidents , Central heating , Damage , Fuels , China , Design , Background radiation , Emergency management , Hazard analysis , Radioactive substances

Heating Start-Up Method and Demonstration for Full Natural Circulation Reactor

Jianhui Yu, Wenji Tan, Xingliang Zhang

ICONE 2022; V004T04A013https://doi.org/10.1115/ICONE29-91535

Abstract

View Articletitled, Heating Start-Up Method and Demonstration for Full Natural Circulation Reactor

PDF

Topics: Heating

Design and Comparison of Drainage Technology Scheme for Multi-Purpose Modular Small Reactor Science and Technology Demonstration Project

Mao Yujia, Sheng Liyuan, Yang Ruobing, Bai Wei, Li Jing

ICONE 2022; V004T04A014https://doi.org/10.1115/ICONE29-91546

Abstract

View Articletitled, Design and Comparison of Drainage Technology Scheme for Multi-Purpose Modular Small Reactor Science and Technology Demonstration Project

PDF

Topics: Design , Drainage , Water

Experimental Study on Measurement Characteristics of Different Type Flow Meters in Pb-Bi Environment

Xin Liu, Xiangyu Yun, Junming Liang, HuiYong Zhang

ICONE 2022; V004T04A015https://doi.org/10.1115/ICONE29-91675

Abstract

View Articletitled, Experimental Study on Measurement Characteristics of Different Type Flow Meters in Pb-Bi Environment

PDF

Topics: Flow (Dynamics) , Flowmeters

Evaluation of Detectability of Pump/Diagrid Link Rupture in Pool-Type Sodium-Cooled Fast Reactor

Yuichi Onoda, Masato Uchita, Minako Tokizaki, Hitoshi Okazaki

ICONE 2022; V004T04A016https://doi.org/10.1115/ICONE29-91688

Abstract

View Articletitled, Evaluation of Detectability of Pump/Diagrid Link Rupture in Pool-Type Sodium-Cooled Fast Reactor

PDF

Topics: Pumps , Rupture , Safety , Signals , Sodium fast reactors

Seismic Analysis of the Scale Reactor Structure Model of a Lead-Bismuth-Cooled ADS Reactor

Gang Rong, He Zhu, Yi Yang

ICONE 2022; V004T04A017https://doi.org/10.1115/ICONE29-91753

Abstract

View Articletitled, Seismic Analysis of the Scale Reactor Structure Model of a Lead-Bismuth-Cooled ADS Reactor

PDF

Topics: Seismic analysis , Annulus , Design , Fluid structure interaction , Leakage , Cavities , Finite element analysis , Fluids , Metals , Shells

Transient Thermal-Hydraulic Analysis for Thermal Load Fluctuation Test Using HTTR

Takeshi Aoki, Hiroyuki Sato

ICONE 2022; V004T04A018https://doi.org/10.1115/ICONE29-91761

Abstract

View Articletitled, Transient Thermal-Hydraulic Analysis for Thermal Load Fluctuation Test Using HTTR

PDF

Topics: Hydrogen production , Thermal loads , Transients (Dynamics) , Very high temperature reactors , Coolants , Temperature , Control systems , Simulation , Carbon , Heat

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Basic Device Specifications

Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Isamu Sato, Haruaki Matsuura, Yoshihiro Sekio, Hiroshi Sagara, Masatoshi Kawashima

ICONE 2022; V004T04A019https://doi.org/10.1115/ICONE29-91812

Abstract

View Articletitled, Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Basic Device Specifications

PDF

Topics: Accidents , Fast neutron reactors , Sodium fast reactors

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

Emre Tatli, Sung Jin Lee, Jun Liao, Paolo Ferroni

ICONE 2022; V004T04A020https://doi.org/10.1115/ICONE29-91821

Abstract

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

PDF

Topics: Cooling , Fast neutron reactors , Computational fluid dynamics , Design , Heat , Reactor vessels , Vessels , Water , Accidents , Accounting

Hydrogen Release Reaction From Sodium Hydride With Different Sample Quantities

Daisuke Doi

ICONE 2022; V004T04A021https://doi.org/10.1115/ICONE29-91847

Abstract

View Articletitled, Hydrogen Release Reaction From Sodium Hydride With Different Sample Quantities

PDF

Topics: Heating , Hydrogen , Sodium , Sodium fast reactors , Thermal analysis

Optimization in Heat Transfer Scheme for Load Rejection and Emergency Shutdown Conditions of Sodium Fast Reactor

Yang Yu, Jun Yang, Jin Wang, Xiaokun Wang, Wenjun Hu, Donghui Zhang

ICONE 2022; V004T04A022https://doi.org/10.1115/ICONE29-91857

Abstract

View Articletitled, Optimization in Heat Transfer Scheme for Load Rejection and Emergency Shutdown Conditions of Sodium Fast Reactor

PDF

Topics: Heat transfer , Optimization , Scram , Sodium fast reactors , Stress

Study on Steady Operational Characteristics of Floating Nuclear Reactor Under Ocean Condition

Kun Cheng, Xiao Chu, Zhifang Qiu, Lin Xian, Jian Deng

ICONE 2022; V004T04A023https://doi.org/10.1115/ICONE29-92063

Abstract

View Articletitled, Study on Steady Operational Characteristics of Floating Nuclear Reactor Under Ocean Condition

PDF

Topics: Nuclear reactors , Oceans

The Research of the Customer Needs of a Type of Innovative Lead-Bismuth Fast Reactor Base on the TRIZ Method

Weiquan Yuan, Zhao Chen, Kangli Shi, Chang Su, Jinghua Tang, Dawei Cui, Chengjie Duan

ICONE 2022; V004T04A024https://doi.org/10.1115/ICONE29-92077

Abstract

View Articletitled, The Research of the Customer Needs of a Type of Innovative Lead-Bismuth Fast Reactor Base on the TRIZ Method

PDF

Topics: Fast neutron reactors

Analysis of EBR-II Loss-of-Flow Transients With 3D Model of CATHARE Code

Xiaolin Chen, Simon Li, Songbai Cheng

ICONE 2022; V004T04A025https://doi.org/10.1115/ICONE29-92109

Abstract

View Articletitled, Analysis of EBR-II Loss-of-Flow Transients With 3D Model of CATHARE Code

PDF

Topics: Accidents , Flow (Dynamics) , Sodium fast reactors , Three-dimensional models , Transients (Dynamics)

Numerical Analysis of Simple Heat Equation to Predict the Opening Time of the Freeze Plug in Molten Salt Reactors

Muhammad Ilham, Tomio Okawa

ICONE 2022; V004T04A026https://doi.org/10.1115/ICONE29-92284

Abstract

View Articletitled, Numerical Analysis of Simple Heat Equation to Predict the Opening Time of the Freeze Plug in Molten Salt Reactors

PDF

Topics: Heat , Molten salt reactors , Numerical analysis

Study on Flow and Heat Transfer Performance of Space Reactor Radiator Water Heat Pipe

Guanghui Jiao, Genglei Xia, Zhou Tao, Yuepeng Bi

ICONE 2022; V004T04A027https://doi.org/10.1115/ICONE29-92516

Abstract

View Articletitled, Study on Flow and Heat Transfer Performance of Space Reactor Radiator Water Heat Pipe

PDF

Topics: Flow (Dynamics) , Heat pipes , Heat transfer , Water

Simulation of Plasma Magnetic Confinement System Based on Modelica Language: Starting with a Single Particle

Hanyang Lyu, Xiang Wang

ICONE 2022; V004T04A028https://doi.org/10.1115/ICONE29-92564

Abstract

View Articletitled, Simulation of Plasma Magnetic Confinement System Based on Modelica Language: Starting with a Single Particle

PDF

Topics: Particulate matter , Plasmas (Ionized gases) , Simulation

Simulation of One-Dimensional Nuclear-Pumped Laser Generation System Based on Modelica Language

Xiang Tang, Xiang Wang

ICONE 2022; V004T04A029https://doi.org/10.1115/ICONE29-92567

Abstract

View Articletitled, Simulation of One-Dimensional Nuclear-Pumped Laser Generation System Based on Modelica Language

PDF

Topics: Lasers , Simulation

Seismic Isolation Reliability Analysis of a Lead-Bismuth Small Modular Reactor

Yi Huang, Min Qi

ICONE 2022; V004T04A030https://doi.org/10.1115/ICONE29-92584

Abstract

View Articletitled, Seismic Isolation Reliability Analysis of a Lead-Bismuth Small Modular Reactor

PDF

Topics: Event history analysis , Small modular reactors

Research on Sensing Value Reconstruction Method of Small Modular Reactor Based on Improved Short-Term and Long-Term Memory Neural Network

Shouyu Cheng, Hao Zhu, Bowen Zhang, Jilin Sun

ICONE 2022; V004T04A031https://doi.org/10.1115/ICONE29-92790

Abstract

View Articletitled, Research on Sensing Value Reconstruction Method of Small Modular Reactor Based on Improved Short-Term and Long-Term Memory Neural Network

PDF

Topics: Artificial neural networks , Small modular reactors

Thermal-Hydraulic Analysis of HL-2M Cooling Water System for Toroidal Field Coils

Jiaqi Wang, Yanfeng Xie, Xiaolong Liu, Jianpeng Meng, Ruibao Jia, Qiang Li, Xin Chen

ICONE 2022; V004T04A032https://doi.org/10.1115/ICONE29-92917

Abstract

View Articletitled, Thermal-Hydraulic Analysis of HL-2M Cooling Water System for Toroidal Field Coils

PDF

Topics: Cooling , Water

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

Yanfei Qiu

ICONE 2022; V004T04A033https://doi.org/10.1115/ICONE29-93201

Abstract

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

PDF

Topics: Design , Modeling , Pressurized water reactors , Cycles , Fuels , Safety , Feedback , Modular construction , Neutrons , Nuclear reactors

Structural Analysis of a Reactor Vessel in a Sodium-Cooled Fast Reactor Under Extremely High Temperature Conditions

Hidemasa Yamano, Satoshi Futagami, Masanori Ando

ICONE 2022; V004T04A034https://doi.org/10.1115/ICONE29-93231

Abstract

View Articletitled, Structural Analysis of a Reactor Vessel in a Sodium-Cooled Fast Reactor Under Extremely High Temperature Conditions

PDF

Topics: Deformation , High temperature , Reactor vessels , Resilience , Sodium fast reactors , Structural analysis

Coolability Evaluation of the Debris Bed on Core Catcher in a Sodium-Cooled Fast Reactor With a Whole Vessel Model

Hidemasa Yamano, Shigenobu Kubo, Kyohei Sasa, Akihiro Shibata, Edouard Hourcade, Jean François Dirat

ICONE 2022; V004T04A035https://doi.org/10.1115/ICONE29-93244

Abstract

View Articletitled, Coolability Evaluation of the Debris Bed on Core Catcher in a Sodium-Cooled Fast Reactor With a Whole Vessel Model

PDF

Topics: Sodium fast reactors , Vessels , Circuits , Cooling systems , Fuels , Accidents , Cooling , Design , Dynamics (Mechanics) , Flow (Dynamics)

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

Zihao Guo, Guang Wang, Genghua Su, Xiuan Shi

ICONE 2022; V004T04A036https://doi.org/10.1115/ICONE29-93256

Abstract

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

PDF

Topics: Design , Irradiation (Radiation exposure) , Neutron flux , Physics , Water , Biomedicine , Isotopes , Cycles , Decontamination , Fuels

Criticality Study of Spent Fuel Storage Rack of Ship-Based Small Modular Reactor

Yaoxin Ye, Jun Zhao, Yunfei Xu

ICONE 2022; V004T04A037https://doi.org/10.1115/ICONE29-93407

Abstract

View Articletitled, Criticality Study of Spent Fuel Storage Rack of Ship-Based Small Modular Reactor

PDF

Topics: Ships , Small modular reactors , Spent fuel storage , Storage , Accidents , Boron , Deformation , Fuel storage , Fuels , Accounting

3d Multi-Physics Numerical Coupling of Monte Carlo Neutronics and Thermal-Hydraulic for Solid Core

Qing Yang, Jianhua Xia, Xiaojing Liu, Qingquan Pan, Hui He, Tengfei Zhang

ICONE 2022; V004T04A038https://doi.org/10.1115/ICONE29-94534

Abstract

View Articletitled, 3d Multi-Physics Numerical Coupling of Monte Carlo Neutronics and Thermal-Hydraulic for Solid Core

PDF

Topics: Physics , Neutrons , Simulation , Computational fluid dynamics , Computer simulation , Conceptual design , Coolants , Design , Nuclear design , Optimization

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