Topics: Fuels , Physics , Molten salt reactors , Fast neutron reactors , Fluids , Liquid metals , Neutrons , Sodium fast reactors , Steady state , Temperature

Unprotected Overpower Transient Analysis of a Million Kilowatt Traveling Wave Reactor Core

Pengrui Qiao, Jian Zhang, Chao Lin

ICONE 2017; V005T05A002https://doi.org/10.1115/ICONE25-66057

Abstract

View Articletitled, Unprotected Overpower Transient Analysis of a Million Kilowatt Traveling Wave Reactor Core

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Topics: Transient analysis , Traveling waves , Fuels , Safety , Accidents , Design , Innovation , Transients (Dynamics) , China , Cladding systems (Building)

Sodium Cooled Fast Bread Reactor HCDA Codes Development

Shi Tai, Zhang Dong-hui, Hu Wen-jun

ICONE 2017; V005T05A003https://doi.org/10.1115/ICONE25-66067

Abstract

View Articletitled, Sodium Cooled Fast Bread Reactor HCDA Codes Development

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Topics: Accidents , China , Leakage , Liquid metal cooled reactors , Nuclear power , Nuclear reactors , Radioactive substances , Sodium

Unprotected Loss of Flow Analysis of a Million Kilowatt Traveling Wave Reactor Core

Wenjun Hu, Pengrui Qiao

ICONE 2017; V005T05A004https://doi.org/10.1115/ICONE25-66101

Abstract

View Articletitled, Unprotected Loss of Flow Analysis of a Million Kilowatt Traveling Wave Reactor Core

PDF

Topics: Flow (Dynamics) , Traveling waves , Fuels , Safety , Accidents , Design , Innovation , China , Cladding systems (Building) , Combustion

Experimental Study of the Sodium-Cooled Fast Reactor Vessel Seismic Analysis Considered the Liquid Sloshing

Hongda Liu, Daogang Lu, Xiaoxuan Li, Xiaojia Zeng, Guangdong Bao

ICONE 2017; V005T05A005https://doi.org/10.1115/ICONE25-66111

Abstract

View Articletitled, Experimental Study of the Sodium-Cooled Fast Reactor Vessel Seismic Analysis Considered the Liquid Sloshing

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Topics: Seismic analysis , Sloshing , Sodium fast reactors , Vessels , Water , Waves , Fast neutron reactors , Pressure , Design , Earthquake resistant design

The Measuring of Sodium Droplet Size Distribution and its Impact on the Consequence of Sodium Spray Fire

Wang Guozhi, Du Haiou, Wang Rongdong, Shi Wentao, Piao Jun

ICONE 2017; V005T05A006https://doi.org/10.1115/ICONE25-66176

Abstract

View Articletitled, The Measuring of Sodium Droplet Size Distribution and its Impact on the Consequence of Sodium Spray Fire

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Topics: Drops , Fire , Sodium , Sprays , Vessels , Pressure , Nozzles , Particle size , Temperature , Approximation

Comparison and Analysis on Two Kinds of Passive Residual Heat Removal System Designs Under Station Blackout Accident for Integral Small Modular Reactor

Fei Li, Feng Shen, Ning Bai, Zhaocan Meng

ICONE 2017; V005T05A007https://doi.org/10.1115/ICONE25-66181

Abstract

View Articletitled, Comparison and Analysis on Two Kinds of Passive Residual Heat Removal System Designs Under Station Blackout Accident for Integral Small Modular Reactor

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Topics: Accidents , Heat , Small modular reactors , Design , Coolants , Hydraulic drive systems , Safety , Simulation models

The R&D Activities and Future Plan of 4MW Hot Cathode Ion Source for EAST Neutral Beam Injector

Yahong Xie, Chundong Hu, Sheng Liu, Jun Li, Yuanlai Xie, Lizhen Liang, Caichao Jiang, Jianglong Wei, Yongjian Xu, Ling Tao, Yuming Gu, Shiyong Chen, Peng Sheng, Zhimin Liu

ICONE 2017; V005T05A008https://doi.org/10.1115/ICONE25-66218

Abstract

View Articletitled, The R&D Activities and Future Plan of 4MW Hot Cathode Ion Source for EAST Neutral Beam Injector

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Topics: Ejectors , Neutral beams , Plasmas (Ionized gases) , Steady state , Tokamaks , Diamonds , Electrons , Feedback , Heating , Hydrogen

Control Scheme Research of 10MW Fluoride Salt Cooled High Temperature Experiment Reactor

Jian Ruan, Yang Zou, Minghai Li, Hongjie Xu

ICONE 2017; V005T05A009https://doi.org/10.1115/ICONE25-66228

Abstract

View Articletitled, Control Scheme Research of 10MW Fluoride Salt Cooled High Temperature Experiment Reactor

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Topics: High temperature , Coolants , Temperature , Flow (Dynamics) , Stress , Control equipment , Temperature control , Transient analysis , Transients (Dynamics) , Air flow

Research on Natural Circulation Flow Characteristics of Floating Nuclear Power Plant in Heaving Motion

Li Ren, Peng Minjun, Xia Genglei, Zhao Yanan

ICONE 2017; V005T05A010https://doi.org/10.1115/ICONE25-66240

Abstract

View Articletitled, Research on Natural Circulation Flow Characteristics of Floating Nuclear Power Plant in Heaving Motion

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Topics: Flow (Dynamics) , Nuclear power stations , Design , Oceans , Oscillations , Pressurized water reactors , Safety , Simulation models

Preliminary Investigation of Pool Sloshing Behavior in a Two-Dimensional Experiment

Li Shuo, Cheng Songbai, Li Kejia, Lin Shaopeng, Zhang Nan

ICONE 2017; V005T05A011https://doi.org/10.1115/ICONE25-66251

Abstract

View Articletitled, Preliminary Investigation of Pool Sloshing Behavior in a Two-Dimensional Experiment

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Topics: Sloshing , Particulate matter , Water , Pressure , Sodium fast reactors , Accidents , Fuels , Nitrogen , Nozzles , China

Neutronics Analyses of Small Compact Prismatic Nuclear Reactors for the Preliminary Design

Xie Yang, Lei Shi, Ding She

ICONE 2017; V005T05A012https://doi.org/10.1115/ICONE25-66290

Abstract

View Articletitled, Neutronics Analyses of Small Compact Prismatic Nuclear Reactors for the Preliminary Design

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Topics: Design , Nuclear reactors , Accidents , Helium , Alloys , Brayton cycle , Energy conversion , Energy resources , Fuels , Graphite

CFD Analysis Technique Development for Wire Contact Effect of Fuel Rods Within Next Generation FBR in Japan

Hironori Nakamura, Kazuhiro Oyama, Satoshi Hayakawa, Tomoaki Ogata, Seiichiro Maeda, Takayuki Ozawa

ICONE 2017; V005T05A013https://doi.org/10.1115/ICONE25-66307

Abstract

View Articletitled, CFD Analysis Technique Development for Wire Contact Effect of Fuel Rods Within Next Generation FBR in Japan

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Topics: Computational fluid dynamics , Fuel rods , Wire , Fuels , Boundary-value problems , Cladding systems (Building) , Geometry , Simulation , Sodium fast reactors , Temperature

Fusion: Go Small to Go Fast

Giorgio Locatelli

ICONE 2017; V005T05A014https://doi.org/10.1115/ICONE25-66353

Abstract

View Articletitled, Fusion: Go Small to Go Fast

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Topics: Combined heat and power , Degrees of freedom , Design , Economics , Fusion reactors , Power stations , Risk , Stress

Characteristics of Thermal-Hydraulic and Heat Transfer in Liquid Windowless Target of ADS

Feng Wang, Qiang Wen, Xue Qin

ICONE 2017; V005T05A015https://doi.org/10.1115/ICONE25-66379

Abstract

View Articletitled, Characteristics of Thermal-Hydraulic and Heat Transfer in Liquid Windowless Target of ADS

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Topics: Heat transfer , Cavitation , Flow (Dynamics) , Fluids , Alloys , Coolants , Design , Interface structure , Pressure , Spallation (Nuclear physics)

The Research of SFR Aerosol Deposition Behavior in Ventilation Ducts

Lei Zhao, Lixia Ren, Wenjun Hu, Shirui Li

ICONE 2017; V005T05A016https://doi.org/10.1115/ICONE25-66384

Abstract

View Articletitled, The Research of SFR Aerosol Deposition Behavior in Ventilation Ducts

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Topics: Aerosols , Ducts , Sodium fast reactors , Ventilation , Particulate matter , Agglomeration (Materials) , Emergencies , Sodium , Turbulence , Channel flow

Status of MELCOR Sodium Models Development

David L. Y. Louie, Larry L. Humphries

ICONE 2017; V005T05A017https://doi.org/10.1115/ICONE25-66524

Abstract

View Articletitled, Status of MELCOR Sodium Models Development

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Topics: Sodium , Accidents , Chemistry , Coolants , Water , Design , Equations of state , Fire , Licensing , Liquid pool fires

New Design of Thorium Molten Salt Reactor Core and Preliminary Safety Analysis

Chen Qi-chang, Si Sheng-yi, Zhao Jin-kun, Bei Hua

ICONE 2017; V005T05A018https://doi.org/10.1115/ICONE25-66533

Abstract

View Articletitled, New Design of Thorium Molten Salt Reactor Core and Preliminary Safety Analysis

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Topics: Design , Molten salt reactors , Safety , Fuels , Steady state , Temperature , Temperature distribution , Transients (Dynamics) , Engineering simulation , Flow (Dynamics)

Toward an Open-Source Neutronics Code for Circulating-Fuel Reactors

Julien de Troullioud de Lanversin, Alexander Glaser, Malte Göttsche

ICONE 2017; V005T05A019https://doi.org/10.1115/ICONE25-66584

Abstract

View Articletitled, Toward an Open-Source Neutronics Code for Circulating-Fuel Reactors

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Topics: Fuels , Molten salt reactors , Algorithms , Computer simulation , Particulate matter , Resolution (Optics) , Simulation

Thermal Hydraulics Analysis of the Fluoride-Salt-Cooled, High-Temperature Reactor

Yao Fu, Qiang Sun, Chong Zhou, Yang Zou

ICONE 2017; V005T05A020https://doi.org/10.1115/ICONE25-66588

Abstract

View Articletitled, Thermal Hydraulics Analysis of the Fluoride-Salt-Cooled, High-Temperature Reactor

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Topics: High temperature , Thermal hydraulics , Transients (Dynamics) , Coolants , Design , Flow (Dynamics) , Heat , Accidents , China , Fuels

Simulated Temperature Profiles for Corrosion Products Deposited in ITER Experimental Loop

Muhammad Arslan, Ma Yan, Muhammad Ali Shahzad, Lei Jinyun, Shahroze Ahmed

ICONE 2017; V005T05A021https://doi.org/10.1115/ICONE25-66695

Abstract

View Articletitled, Simulated Temperature Profiles for Corrosion Products Deposited in ITER Experimental Loop

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Topics: Corrosion , Temperature profiles , Temperature , Coolants , Temperature distribution , Particulate matter , Pressure , Thermocouples

Simulations of Interfacial Dynamics of Rising Bubble in Liquid LBE Alloy Based on Diffuse-Interface Method

Chuntao Wang, Jiejin Cai

ICONE 2017; V005T05A022https://doi.org/10.1115/ICONE25-66753

Abstract

View Articletitled, Simulations of Interfacial Dynamics of Rising Bubble in Liquid LBE Alloy Based on Diffuse-Interface Method

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Topics: Alloys , Bubbles , Dynamics (Mechanics) , Simulation , Computer simulation , Deformation , Flow (Dynamics) , Nitrogen , Simulation results

Thermal-Hydraulic Analysis of the EBR-II SHRT-45R Unprotected Loss of Flow Experiment With Modified RELAP5

Tang Simiao, Song Jian, Zhang Dalin, Wang Chenglong, Qiu Suizheng, Su Guanghui, Tian Wenxi

ICONE 2017; V005T05A023https://doi.org/10.1115/ICONE25-66766

Abstract

View Articletitled, Thermal-Hydraulic Analysis of the EBR-II SHRT-45R Unprotected Loss of Flow Experiment With Modified RELAP5

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Topics: Flow (Dynamics) , Sodium fast reactors , Accidents , Feedback , Coolants , Temperature , Fuels , Pumps , Safety , Sodium

Conceptual Core Design of Breeding BWR

Rui Guo, Akifumi Yamaji

ICONE 2017; V005T05A024https://doi.org/10.1115/ICONE25-66829

Abstract

View Articletitled, Conceptual Core Design of Breeding BWR

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Topics: Boiling water reactors , Design , Water , Light water reactors , Fuels , Manufacturing , Neutrons , Atoms , Coolants , Cooling

Development of Security and Safety Fuel for Pu-Burner HTGR: Part 3 — Preliminary Reactor Safety Analyses Under Depressurization Accidents

Masaaki Nakano, Kazutaka Ohashi, Koji Okamoto

ICONE 2017; V005T05A025https://doi.org/10.1115/ICONE25-66907

Abstract

View Articletitled, Development of Security and Safety Fuel for Pu-Burner HTGR: Part 3 — Preliminary Reactor Safety Analyses Under Depressurization Accidents

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Topics: Accidents , Fuels , Safety , Security , Very high temperature reactors , Design , Scram , Uranium , Accident management , Combustion

Breeding Properties Study on High Power Thorium Molten Salt Reactor

Yafen Liu, Rui Guo, Xiangzhou Cai, Rui Yan, Yang Zou, Bo Zhou

ICONE 2017; V005T05A026https://doi.org/10.1115/ICONE25-66961

Abstract

View Articletitled, Breeding Properties Study on High Power Thorium Molten Salt Reactor

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Topics: Molten salt reactors , Breeder reactors , Fluids , Fuels , Generation IV reactors , Security , Temperature , Transients (Dynamics)

Application of the Probability-Based Safety Analysis for the Reliability Evaluation of a Special Fuel Salt Release System Design in the Molten Salt Reactor

Yang Qun, Li Minghai, Hou Jie, He Zhaozhong, Chen Kun

ICONE 2017; V005T05A027https://doi.org/10.1115/ICONE25-67017

Abstract

View Articletitled, Application of the Probability-Based Safety Analysis for the Reliability Evaluation of a Special Fuel Salt Release System Design in the Molten Salt Reactor

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Topics: Design , Fuels , Molten salt reactors , Probability , Reliability , Safety , Failure , Accidents , Errors , Human reliability analysis

Development of Security and Safety Fuel for Pu-Burner HTGR: Part 4 — Study on 3S-TRISO Fuel Fabrication

Yohei Saiki, Masaki Honda, Masashi Takahashi, Koichi Ohira, Koji Okamoto

ICONE 2017; V005T05A028https://doi.org/10.1115/ICONE25-67048

Abstract

View Articletitled, Development of Security and Safety Fuel for Pu-Burner HTGR: Part 4 — Study on 3S-TRISO Fuel Fabrication

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Topics: Fuels , Manufacturing , Safety , Security , Very high temperature reactors , Particulate matter , Coating processes , Coatings , High temperature , Fluidized beds

Obstructed View Factor Calculations in Closed Cavities Using Radiation Heat Transfer

Fiaz Mahmood, Huasi Hu

ICONE 2017; V005T05A029https://doi.org/10.1115/ICONE25-67092

Abstract

View Articletitled, Obstructed View Factor Calculations in Closed Cavities Using Radiation Heat Transfer

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Topics: Cavities , Heat transfer , Radiation (Physics) , Pellet fusion , Geometry , X-rays , Errors , Laser beams , Shades and shadows , String

Research and Design of the Sodium Steam Filter System in Large Liquid Metal Cooled Fast Reactors

Wang Leijian, Lu Yuan, Xiao Changzhi

ICONE 2017; V005T05A030https://doi.org/10.1115/ICONE25-67094

Abstract

View Articletitled, Research and Design of the Sodium Steam Filter System in Large Liquid Metal Cooled Fast Reactors

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Topics: Design , Fast neutron reactors , Filters , Liquid metals , Sodium , Steam , Filtration , Valves , Atoms , Chemical properties

Development of Security and Safety Fuel for Pu-Burner HTGR: Part 2 — Design Study of Fuel and Reactor Core

Minoru Goto, Shohei Ueta, Jun Aihara, Yoshitomo Inaba, Yuji Fukaya, Yukio Tachibana, Koji Okamoto

ICONE 2017; V005T05A031https://doi.org/10.1115/ICONE25-67110

Abstract

View Articletitled, Development of Security and Safety Fuel for Pu-Burner HTGR: Part 2 — Design Study of Fuel and Reactor Core

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Topics: Design , Fuels , Safety , Security , Very high temperature reactors , Pressure , Oxygen , Coating processes , Coatings , Failure

Analysis of the Effect of Beam Divergence Angle on Back-Streaming Electron Region in Ion Source for EAST-NBI

Chundong Hu, Mingshan Wu, Yahong Xie, Jianglong Wei, Ling Yu

ICONE 2017; V005T05A032https://doi.org/10.1115/ICONE25-67125

Abstract

View Articletitled, Analysis of the Effect of Beam Divergence Angle on Back-Streaming Electron Region in Ion Source for EAST-NBI

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Topics: Electrons , Silencers , Emissions , Ions , Plasmas (Ionized gases) , Safety , Diamonds , Electron emission , Geometry , Heat

Analysis of Sustainable Thorium Fuel Utilization in Molten Salt Reactors Starting From Enriched Uranium

Deyang Cui, Xiangzhou Cai, Jingen Chen, Chenggang Yu

ICONE 2017; V005T05A033https://doi.org/10.1115/ICONE25-67177

Abstract

View Articletitled, Analysis of Sustainable Thorium Fuel Utilization in Molten Salt Reactors Starting From Enriched Uranium

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Topics: Fuels , Molten salt reactors , Sustainability , Uranium , Nuclear fuel cycle , Light water reactors , Breeder reactors , Energy generation , Energy sustainability , Industrial research

Thermodynamic Performance of 5MW Space Nuclear Power System Based on Liquid Metal Rankine Cycle

Xian-Wei Cheng, Hao-Chun Zhang, Xiao-Qi Li, Chen-Xu Zhang, Guang-Bo Zhao

ICONE 2017; V005T05A034https://doi.org/10.1115/ICONE25-67265

Abstract

View Articletitled, Thermodynamic Performance of 5MW Space Nuclear Power System Based on Liquid Metal Rankine Cycle

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Topics: Liquid metals , Nuclear power , Rankine cycle , Exergy , Energy dissipation , Fast neutron reactors , Lithium , Power conversion systems , Power systems (Machinery) , Temperature

Neutronic Analyses for CFETR With Modular Helium Cooled Lithium Ceramic Blanket

Kun Xu, Minyou Ye, Yuntao Song, Mingzhun Lei, Shifeng Mao

ICONE 2017; V005T05A035https://doi.org/10.1115/ICONE25-67291

Abstract

View Articletitled, Neutronic Analyses for CFETR With Modular Helium Cooled Lithium Ceramic Blanket

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Topics: Ceramics , Helium , Lithium , Design , China , Energy generation , Tokamaks , Vacuum , Vessels , Bridges (Structures)

Molecular Dynamics Simulations of Damage Cascades Creation in Oxide-Particle-Embedded Fe

A. M. Mustafa, Zhongyu Li, Lin Shao

ICONE 2017; V005T05A036https://doi.org/10.1115/ICONE25-67356

Abstract

View Articletitled, Molecular Dynamics Simulations of Damage Cascades Creation in Oxide-Particle-Embedded Fe

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Topics: Damage , Molecular dynamics simulation , Particulate matter , Alloys , Cascades (Fluid dynamics) , Explosions , High temperature , Irradiation (Radiation exposure) , Modeling , Oxygen

Void Reactivity Effect Research on Liquid Metal Cooled Fast Reactor

Yang Lyu, Xiao Liang

ICONE 2017; V005T05A037https://doi.org/10.1115/ICONE25-67368

Abstract

View Articletitled, Void Reactivity Effect Research on Liquid Metal Cooled Fast Reactor

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Topics: Fast neutron reactors , Liquid metals , Bubbles , Computational methods , Coolants , Design , Fuels , Industrial research , Liquid metal cooled reactors , Nuclear industry

Reinforcement of Emergency Power Supply System for Next Generation SFR

Nobuyuki Ishikawa, Yoshitaka Chikazawa, Daisuke Sato, Risako Ikari

ICONE 2017; V005T05A038https://doi.org/10.1115/ICONE25-67369

Abstract

View Articletitled, Reinforcement of Emergency Power Supply System for Next Generation SFR

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Topics: Emergency power , Sodium fast reactors , Design , Generators , Cooling systems , Emergencies , Optimization , Accidents , Diesel generators , Fuels

Commissioning of CIRCE Facility for SGTR Experimental Investigation for HLMRs and Pre-Test Analysis by SIMMER-IV Code

Alessio Pesetti, Mariano Tarantino, Piero Gaggini, Giuseppe Polazzi, Nicola Forgione

ICONE 2017; V005T05A039https://doi.org/10.1115/ICONE25-67419

Abstract

View Articletitled, Commissioning of CIRCE Facility for SGTR Experimental Investigation for HLMRs and Pre-Test Analysis by SIMMER-IV Code

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Topics: Boilers , Control equipment , Control systems , Data acquisition , Disks , Eutectic alloys , Flow (Dynamics) , Heat exchangers , Hot water heating , Hydraulic lifts

Experimental Investigation in LIFUS5/Mod2 Facility of Spiral-Tube Steam Generator Rupture Scenarios for ELFR

Alessio Pesetti, Alessandro Del Nevo, Andrea Neri, Stefano Cati, Valerio Sermenghi, Massimo Valdiserri, Daniel Giannotti, Mariano Tarantino, Nicola Forgione

ICONE 2017; V005T05A040https://doi.org/10.1115/ICONE25-67420

Abstract

View Articletitled, Experimental Investigation in LIFUS5/Mod2 Facility of Spiral-Tube Steam Generator Rupture Scenarios for ELFR

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Topics: Boilers , Rupture , Water , Strain gages , Vessels , Data acquisition systems , Deformation , Ejectors , Eutectic alloys , Evaporation

HERO Test Section for Experimental Investigation of Steam Generator Bayonet Tube of ALFRED

Davide Rozzia, Alessio Pesetti, Alessandro Del Nevo, Mariano Tarantino, Nicola Forgione

ICONE 2017; V005T05A041https://doi.org/10.1115/ICONE25-67422

Abstract

View Articletitled, HERO Test Section for Experimental Investigation of Steam Generator Bayonet Tube of ALFRED

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Topics: Boilers , Water , Flow (Dynamics) , Heat exchangers , Pressure transducers , Steam , Feedwater , Helium , Pipes , Superheating

Methodology to Investigate Vibration Phenomena Caused by the Steam Condensation at Subatmospheric Condition

R. Lo Frano, D. Mazed, D. Aquaro, D. Del Serra, I. Sekachev, G. Giambartolomei

ICONE 2017; V005T05A042https://doi.org/10.1115/ICONE25-67448

Abstract

View Articletitled, Methodology to Investigate Vibration Phenomena Caused by the Steam Condensation at Subatmospheric Condition

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Topics: Condensation , Steam , Vibration , Water , Oscillations , Safety , Accidents , Boiling water reactors , Finite element methods , Finite element model

A Simulation of Small Break Loss of Coolant Accident (SB-LOCA) in AP1000 Nuclear Power Plant Using RELAP5-MV

Eltayeb Yousif, Zhang Zhijian, Tian Zhao-fei, A. M. Mustafa

ICONE 2017; V005T05A043https://doi.org/10.1115/ICONE25-67469

Abstract

View Articletitled, A Simulation of Small Break Loss of Coolant Accident (SB-LOCA) in AP1000 Nuclear Power Plant Using RELAP5-MV

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Topics: Accidents , Coolants , Nuclear power stations , Simulation , Computer software , Modeling , Nuclear power , Thermal hydraulics , Transients (Dynamics) , Computer programming

Considerations on a Validation Matrix for System Analysis Codes of Pebble Bed Modular HTRs

Feng Gou, Fubing Chen, Yujie Dong

ICONE 2017; V005T05A044https://doi.org/10.1115/ICONE25-67492

Abstract

View Articletitled, Considerations on a Validation Matrix for System Analysis Codes of Pebble Bed Modular HTRs

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Topics: Systems analysis , Accidents , China , Design , High temperature , Power stations , Regulations , Safety , Thermal hydraulics

Investigation of Air Ingress Into a Vacuum Vessel Related to Particle Re-Suspension and Distribution for Dust Issues in ITER

Emmanuel Porcheron, Pascal Lemaitre

ICONE 2017; V005T05A045https://doi.org/10.1115/ICONE25-67496

Abstract

View Articletitled, Investigation of Air Ingress Into a Vacuum Vessel Related to Particle Re-Suspension and Distribution for Dust Issues in ITER

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Topics: Dust , Particulate matter , Vacuum , Vessels , Accidents , Hydrogen , Pressure , Tokamaks , Containment , Coolants

Emergency Strategy Research of Loss of Coolant Accident for Small Modular Reactor

Wang Yuqi, Yu Aimin, Yang Qingming

ICONE 2017; V005T05A046https://doi.org/10.1115/ICONE25-67528

Abstract

View Articletitled, Emergency Strategy Research of Loss of Coolant Accident for Small Modular Reactor

PDF

Topics: Accidents , Coolants , Emergencies , Small modular reactors , Safety , Cooling , Industrial research , Modeling , Simulation , Vessels

Development of Security and Safety Fuel for Pu-Burner HTGR: Part 5 — Test and Characterization for ZrC Coating

Shohei Ueta, Jun Aihara, Minoru Goto, Yukio Tachibana, Koji Okamoto

ICONE 2017; V005T05A047https://doi.org/10.1115/ICONE25-67530

Abstract

View Articletitled, Development of Security and Safety Fuel for Pu-Burner HTGR: Part 5 — Test and Characterization for ZrC Coating

PDF

Topics: Coating processes , Coatings , Fuels , Safety , Security , Very high temperature reactors , Particulate matter , Electron microscopes , Gases , Weight (Mass)

Development and Validation of Evaluation Method on Hypothetical Total Instantaneous Flow Blockage in Sodium-Cooled Fast Reactors and its Application to a Middle Size SFR

Yoshitaka Fukano

ICONE 2017; V005T05A048https://doi.org/10.1115/ICONE25-67559

Abstract

View Articletitled, Development and Validation of Evaluation Method on Hypothetical Total Instantaneous Flow Blockage in Sodium-Cooled Fast Reactors and its Application to a Middle Size SFR

PDF

Topics: Evaluation methods , Flow (Dynamics) , Sodium fast reactors , Control systems , Safety , Coolants , Fuels , Light water reactors , Signals

Development of the Severe Accident Evaluation Method on Second Coolant Leakages From the PHTS in a Loop-Type Sodium-Cooled Fast Reactor

Fumiaki Yamada, Yuya Imaizumi, Masahiro Nishimura, Yoshitaka Fukano, Mitsuhiro Arikawa

ICONE 2017; V005T05A049https://doi.org/10.1115/ICONE25-67581

Abstract

View Articletitled, Development of the Severe Accident Evaluation Method on Second Coolant Leakages From the PHTS in a Loop-Type Sodium-Cooled Fast Reactor

PDF

Topics: Accidents , Coolants , Evaluation methods , Leakage , Sodium fast reactors , Sodium , Countermeasures , Heat , Reactor vessels , Transients (Dynamics)

Uncertainty Analysis for Source Term Evaluation of High Temperature Gas-Cooled Reactor Under Accident Conditions: Identification of Influencing Factors in Loss-of-Forced Circulation Accidents

Yuki Honda, Hiroyuki Sato, Shigeaki Nakagawa, Hirofumi Ohashi

ICONE 2017; V005T05A050https://doi.org/10.1115/ICONE25-67587

Abstract

View Articletitled, Uncertainty Analysis for Source Term Evaluation of High Temperature Gas-Cooled Reactor Under Accident Conditions: Identification of Influencing Factors in Loss-of-Forced Circulation Accidents

PDF

Topics: Accidents , Uncertainty analysis , Very high temperature reactors , Uncertainty , Risk , Cycles , Dynamics (Mechanics) , Failure , Fuels , Probabilistic risk assessment

Thermo-Hydraulic Research for Supercritical Water Reactor During Power-Raising Phase of Startup

Li Zichao, Zhou Tao, Zhou Lanyu, Liu Liang, Chen Juan, Yu Hongxing

ICONE 2017; V005T05A051https://doi.org/10.1115/ICONE25-67595

Abstract

View Articletitled, Thermo-Hydraulic Research for Supercritical Water Reactor During Power-Raising Phase of Startup

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Topics: Supercritical water reactors , Coolants , Temperature , Heat transfer , Feedwater , Flow (Dynamics) , Pressure , Security , Thermal properties

Simulation Calculation of the Core Physical Characteristics of China Experimental Fast Reactor With MCNP

Xiong Wen-bin, Cao Jian, Xie Qin, Wang Zhan-yong, Wang Chuang, Li Hu-wei, Yang Sen-gai, Mao Huan, Wang Jing

ICONE 2017; V005T05A052https://doi.org/10.1115/ICONE25-67729

Abstract

View Articletitled, Simulation Calculation of the Core Physical Characteristics of China Experimental Fast Reactor With MCNP

PDF

Topics: China , Fast neutron reactors , Simulation , Safety , Design , Reliability

Theoretical and Experimental Research on the Single-Phase and Incipient Boiling Heat Transfer of Liquid Metal Sodium

Dalin Zhang, Jing Chen, Ping Song, Shibao Wang, Xin'an Wang, Linfeng Li, Suizheng Qiu, G. H. Su

ICONE 2017; V005T05A053https://doi.org/10.1115/ICONE25-67865

Abstract

View Articletitled, Theoretical and Experimental Research on the Single-Phase and Incipient Boiling Heat Transfer of Liquid Metal Sodium

PDF

Topics: Boiling , Heat transfer , Liquid metals , Sodium , Sodium fast reactors , Annulus , Critical heat flux , Friction , Coolants , Design

The Concept Study on the New Steam Cooling Reactor

Xuesong Yan, Xunchao Zhang, Yaling Zhang, Yangyang Yang, Lei Yang, Wenshan Duan

ICONE 2017; V005T05A054https://doi.org/10.1115/ICONE25-67868

Abstract

View Articletitled, The Concept Study on the New Steam Cooling Reactor

PDF

Topics: Coolants , Cooling , Heat , Monte Carlo methods , Neutrons , Nuclear fission , Nuclear reactors , Particulate matter , Steam , Temperature

Development of Manufacturing Technologies for the ITER Toroidal Field Coil: Insertion Processes of Conductors

K. Yamamoto, T. Matsumoto, T. Baba, A. Yamamoto, S. Kanbayashi, T. Kagawa, T. Okamoto, S. Fujii, S. Ando, K. Matsui, M. Nakahira, N. Koizumi

ICONE 2017; V005T05A055https://doi.org/10.1115/ICONE25-67986

Abstract

View Articletitled, Development of Manufacturing Technologies for the ITER Toroidal Field Coil: Insertion Processes of Conductors

PDF

Topics: Deformation , Dimensions , Errors , Fiber lasers , Forging , Gas tungsten arc welding , Heat treating (Metalworking) , Laser welding , Machining , Manufacturing

Loading Scheme Research of Small Modular Sodium Cooled Reactor in a Factory

Hu Xiao, Chen Xiao Liang

ICONE 2017; V005T05A056https://doi.org/10.1115/ICONE25-67988

Abstract

View Articletitled, Loading Scheme Research of Small Modular Sodium Cooled Reactor in a Factory

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Topics: Sodium , Sensors , Neutron sources , China , Fuels , Reactor vessels , Simulation , Chemical properties , Construction , Fast neutron reactors

Determination of Convective Heat Transfer Coefficients in the Core of the Pebble-Bed Fluoride-Salt-Cooled High Temperature Reactor Using Frequency Response Techniques

Lakshana Huddar, Brandon Kuhnert, Ali James Albaaj, Connie Lee, Per F. Peterson

ICONE 2017; V005T05A057https://doi.org/10.1115/ICONE25-67992

Abstract

View Articletitled, Determination of Convective Heat Transfer Coefficients in the Core of the Pebble-Bed Fluoride-Salt-Cooled High Temperature Reactor Using Frequency Response Techniques

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Topics: Convection , Frequency response , High temperature , Fluids , Temperature , Heat transfer coefficients , Coolants , Copper , Dynamic response , Heat transfer

Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues

Application Differences of In-Service Inspection Regulations Between RSE-M2010 and ASME Section XI in China PWRs

Yang Cheng, Zhang Xueliang, Xia Peng, Zeng Qingyue, Li Tian

ICONE 2017; V005T07A001https://doi.org/10.1115/ICONE25-66028

Abstract

View Articletitled, Application Differences of In-Service Inspection Regulations Between RSE-M2010 and ASME Section XI in China PWRs

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Topics: China , In-service inspection , Pressurized water reactors , Regulations , Nuclear power , Innovation , Inspection , Licensing , Nondestructive evaluation , Nuclear industry

Study on the Indication Processing Method for the In-Service Inspection Based on RSE-M

Xia Peng, Zhang Xueliang, Yang Cheng, Zeng Qingyue

ICONE 2017; V005T07A002https://doi.org/10.1115/ICONE25-66138

Abstract

View Articletitled, Study on the Indication Processing Method for the In-Service Inspection Based on RSE-M

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Topics: In-service inspection , China , Fatigue cracks , Nondestructive evaluation , Pressurized water reactors

The Application of Piping Material Code in the CAP1400 Nuclear Plant Project

Shen Jie, Zhang Zhen-ning, Liu Yu

ICONE 2017; V005T07A003https://doi.org/10.1115/ICONE25-66642

Abstract

View Articletitled, The Application of Piping Material Code in the CAP1400 Nuclear Plant Project

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Topics: Nuclear power stations , Pipes , Design , Nuclear power , Nuclear engineering , Nuclear industry

Nonlinear Finite Element Analysis of Class 1 Pressure Vessels

Mingya Chen, Weiwei Yu, Jinhua Shi, Feng Lu

ICONE 2017; V005T07A004https://doi.org/10.1115/ICONE25-66910

Abstract

View Articletitled, Nonlinear Finite Element Analysis of Class 1 Pressure Vessels

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Topics: Finite element analysis , Pressure vessels , Stress , Design , Nozzles , Elastic analysis , Failure , Pipes , Reactor vessels , ASME Standards

The European Utility Requirements for Advanced Light Water Reactors (EUR): Recent Achievements and New Challenges

Guillaume Jacquart, Olli Kymäläinen, Jean-François Vivier, Giovanni Ferraro, Emmanuel Vieilletoile

ICONE 2017; V005T07A005https://doi.org/10.1115/ICONE25-67141

Abstract

View Articletitled, The European Utility Requirements for Advanced Light Water Reactors (EUR): Recent Achievements and New Challenges

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Topics: Light water reactors , Design , Nuclear power stations , Safety , Engineering standards , Fukushima nuclear disaster, Japan, 2011 , Hazards , Instrumentation , Public utilities

Requirement and Discussion of Design Extension Conditions

Yan Jinquan, Chen Song, Tian Lin, Wang Minglu

ICONE 2017; V005T07A006https://doi.org/10.1115/ICONE25-67529

Abstract

View Articletitled, Requirement and Discussion of Design Extension Conditions

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Topics: Design , Safety , Accidents , Nuclear power stations , China , Nuclear power , Radioisotopes

The Integrated Management System for New Nuclear Power Projects: Requirements of IAEA Safety Standards

Li Xiaoping

ICONE 2017; V005T07A007https://doi.org/10.1115/ICONE25-67572

Abstract

View Articletitled, The Integrated Management System for New Nuclear Power Projects: Requirements of IAEA Safety Standards

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Topics: Nuclear power , Safety , Accidents , Cycles , Decision making , Design , Fukushima nuclear disaster, Japan, 2011 , Leadership , Nuclear decommissioning , Nuclear power stations

Status of the JSME Codification Activities on Tornado-Generated Missile Protection for Structures of Nuclear Power Plants

Koji Shirai, Masuhiro Beppu, Hideo Hirai, Kazuhiko Yamada, Shinichi Yoshida, Yohei Shinohara

ICONE 2017; V005T07A008https://doi.org/10.1115/ICONE25-67776

Abstract

View Articletitled, Status of the JSME Codification Activities on Tornado-Generated Missile Protection for Structures of Nuclear Power Plants

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Topics: Japan Society of Mechanical Engineers , Missiles , Nuclear power stations , Design , Stress , Dynamics (Mechanics) , Earthquakes , Steel , Acceptance criteria , Computers