Topics: Accidents , Diffusion (Physics) , Transportation systems , Chemical properties , Chemical reactions , Leakage , Nuclear fuel cycle , Plumes (Fluid dynamics) , Vapors

A Movable Device of Explosives Detection

Zheng Yan, Tong Ti, Jing Shi-wei, Li Huan-yu, Liu Xuan, Gao Ya-dong, Nian Rui-xue

ICONE 2017; V004T06A003https://doi.org/10.1115/ICONE25-66070

Abstract

View Articletitled, A Movable Device of Explosives Detection

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Topics: Explosives , Particulate matter , Sensors , Electromagnetic scattering , Neutron generators , Neutrons , Organic compounds , Radiation scattering , Resolution (Optics) , Scattering (Physics)

Constrained Least Squares Method Used in Nuclear Accident Source Term Inversion

Wang Xuan, Du Fenglei, Huang Xiaodong

ICONE 2017; V004T06A004https://doi.org/10.1115/ICONE25-66083

Abstract

View Articletitled, Constrained Least Squares Method Used in Nuclear Accident Source Term Inversion

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Topics: Accidents , Algorithms , Diffusion (Physics) , Simulation results , Chernobyl Nuclear Accident, Chornobyl, Ukraine, 1986 , China , Errors , Failure , Feedback , Fukushima nuclear disaster, Japan, 2011

Data Assimilation for Fukushima Nuclear Accident Assessments

Mei Xu, Biao Yuan, Liangyu Wang, Lijun Zhang

ICONE 2017; V004T06A005https://doi.org/10.1115/ICONE25-66102

Abstract

View Articletitled, Data Assimilation for Fukushima Nuclear Accident Assessments

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Topics: Fukushima nuclear disaster, Japan, 2011 , Accidents , Radiation (Physics) , Algorithms , Errors , Uncertainty , Diffusion (Physics) , Kalman filters , Nuclear power stations , Radioactive substances

Research of Debris Blocking in PWR Vessel After LOCA

Yang Jiang, Huang Xi

ICONE 2017; V004T06A006https://doi.org/10.1115/ICONE25-66134

Abstract

View Articletitled, Research of Debris Blocking in PWR Vessel After LOCA

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Topics: Pressurized water reactors , Vessels , Nuclear power stations , Cooling , Safety

Modeling of QUENCH 10 Experiment on Air Ingress Using RELAP/SCDAPSIM Mod 3.5

Tadas Kaliatka, Eugenijus Uspuras, Chris M. Allison

ICONE 2017; V004T06A007https://doi.org/10.1115/ICONE25-66135

Abstract

View Articletitled, Modeling of QUENCH 10 Experiment on Air Ingress Using RELAP/SCDAPSIM Mod 3.5

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Topics: Accident management , Accidents , Computers , Light water reactors , Modeling , Oxidation , Steam , Transients (Dynamics) , Water , Zirconium

The Comparative Advantages of CAP1400 Nuclear Power Plant Passive Safety System

Ye Cheng, Wang Minglu, Qiu Zhongming, Wang Yong

ICONE 2017; V004T06A008https://doi.org/10.1115/ICONE25-66182

Abstract

View Articletitled, The Comparative Advantages of CAP1400 Nuclear Power Plant Passive Safety System

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Topics: Nuclear power stations , Safety , Containment , Concretes , Cooling systems , Nuclear power , Probabilistic safety assessment , Sprays

Issues on Radiation Safety Supervision of Radioactive Material Transportation in China

Wang Xuexin, Wei Weiqiang, Tang Rongyao, Sun Hongchao, Zhuang Dajie, Wang Renze, Sun Shutang, Meng Dongyuan, Yan Feng, Li Guoqiang

ICONE 2017; V004T06A009https://doi.org/10.1115/ICONE25-66310

Abstract

View Articletitled, Issues on Radiation Safety Supervision of Radioactive Material Transportation in China

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Topics: China , Radiation (Physics) , Radioactive substances , Safety , Transportation systems , Radiation measurement , Contamination , Neutrons , Optimization , Sensors

The Current Research Status and Technical Development Framework of Multi-Reactor Probabilistic Consequence Assessment

Hongchun Ding, Jiejuan Tong, Liguo Zhang, Lu Wang, Ruiying Wang

ICONE 2017; V004T06A010https://doi.org/10.1115/ICONE25-66365

Abstract

View Articletitled, The Current Research Status and Technical Development Framework of Multi-Reactor Probabilistic Consequence Assessment

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Topics: Accidents , Emergency management , Fukushima nuclear disaster, Japan, 2011 , Nuclear power stations , Probabilistic risk assessment , Regulations , Risk , Safety , Spent nuclear fuels

Online Fault Diagnosis of Nuclear Power Plants Using Signed Directed Graph and Fuzzy Theory

Guohua Wu, Liguo Zhang, Jiejuan Tong

ICONE 2017; V004T06A011https://doi.org/10.1115/ICONE25-66367

Abstract

View Articletitled, Online Fault Diagnosis of Nuclear Power Plants Using Signed Directed Graph and Fuzzy Theory

PDF

Topics: Fault diagnosis , Nuclear power stations , Modeling , Simulation experiments , Complex systems , Flaw detection , Radioactivity , Safety , Signal processing

A New Low Enrichment Uranium Core Design of MNSR

Wang Mengjiao, Li Yiguo, Wu Xiaobo, Peng Dan, Hong Jingyan, Hao Qian, Zhang Jinhua, Lu Jin

ICONE 2017; V004T06A012https://doi.org/10.1115/ICONE25-66518

Abstract

View Articletitled, A New Low Enrichment Uranium Core Design of MNSR

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Topics: Design , Uranium , Fuels , Engineering prototypes , Neutrons , Safety , China , Construction , Neutron sources , Nuclear power

Discussion on Application of Accident Sequence Precursor Analysis in China

Jiang Hu, Guoxu Zhang, Yushu Zhang, Binbin Zhang, Zhi Xiao

ICONE 2017; V004T06A013https://doi.org/10.1115/ICONE25-66579

Abstract

View Articletitled, Discussion on Application of Accident Sequence Precursor Analysis in China

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Topics: Accidents , China , Nuclear power stations , Damage , Risk , Cooling , Feedback , Risk assessment

Simulation of Small Steam Generator Tube Break (SSGTB) in a Small Pressurized Water Reactor (SPWR)

Huasong Cao

ICONE 2017; V004T06A014https://doi.org/10.1115/ICONE25-66637

Abstract

View Articletitled, Simulation of Small Steam Generator Tube Break (SSGTB) in a Small Pressurized Water Reactor (SPWR)

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Topics: Boilers , Pressurized water reactors , Simulation , Temperature , Coolants , Corrosion , Design , Flow (Dynamics) , Pressure , Pumps

Analysis and Validation of Wilks Nonparametric Uncertainty Method for Best-Estimate Calculations in Nuclear Safety

Deng Cheng-Cheng, Liu Wei-Li, Yang Jun, Wu Qiao

ICONE 2017; V004T06A015https://doi.org/10.1115/ICONE25-66655

Abstract

View Articletitled, Analysis and Validation of Wilks Nonparametric Uncertainty Method for Best-Estimate Calculations in Nuclear Safety

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Topics: Safety , Uncertainty , Emergency core cooling systems , Stability , Accidents , Flow (Dynamics) , Nuclear power stations , Response surface methodology , Uncertainty analysis , Uncertainty quantification

Preliminary Safety Analysis of a Compact Small Reactor: Feedwater Line Break and Small-Break LOCA Accident Analysis

Linsen Li, Feng Shen, Mian Xing, Zhan Liu, Zhanfei Qi

ICONE 2017; V004T06A016https://doi.org/10.1115/ICONE25-66664

Abstract

View Articletitled, Preliminary Safety Analysis of a Compact Small Reactor: Feedwater Line Break and Small-Break LOCA Accident Analysis

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Topics: Accidents , Feedwater , Safety , Design , Coolants , Cooling systems , Pressurized water reactors , Damage , Optimization , Vessels

Experimental Investigation on Aerosols Collection Performance of Metal Fiber Filter in FCVS

Ding Tao, Yan Changqi, Cao Xiaxin, Guo Zehua

ICONE 2017; V004T06A017https://doi.org/10.1115/ICONE25-66671

Abstract

View Articletitled, Experimental Investigation on Aerosols Collection Performance of Metal Fiber Filter in FCVS

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Topics: Aerosols , Filters , Metal fibers , Filtration , Flow (Dynamics) , Particle size , Containment , Diffusion (Physics) , Gravity (Force) , Inertia (Mechanics)

Preliminary Large Break LOCA and SGTR Accident Analysis of the Compact Small Reactor

Mian Xing, Linsen Li, Feng Shen, Xiao Hu, Zhan Liu, Zhanfei Qi

ICONE 2017; V004T06A018https://doi.org/10.1115/ICONE25-66672

Abstract

View Articletitled, Preliminary Large Break LOCA and SGTR Accident Analysis of the Compact Small Reactor

PDF

Topics: Accidents , Safety , Design , Boilers , Coolants , Cooling , Cooling systems , Damage , Robustness , Rupture

Development of Hydrogen Treatment System in Severe Accident: Part 3 — Study of Reactant Diameter Effect on Hydrogen Treatment

Akira Yamada, Chikako Iwaki, Ryoma Fujihara, Motoshige Yagyu, Masato Okamura, Masashi Tanabe

ICONE 2017; V004T06A019https://doi.org/10.1115/ICONE25-66707

Abstract

View Articletitled, Development of Hydrogen Treatment System in Severe Accident: Part 3 — Study of Reactant Diameter Effect on Hydrogen Treatment

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Topics: Accidents , Hydrogen , Manganese dioxide , Metals , Containment vessels , Heat , Light water reactors , Oxidation , Oxygen , Pressure

The Finite Element Method for Retention System of Radioactive Material Transport Package

Meng Dongyuan, Wang Renze, Zhang Jiangang, Li Guoqiang, Zhuang Dajie, Sun Hongchao, Wang Xuexin, Sun Shutang

ICONE 2017; V004T06A020https://doi.org/10.1115/ICONE25-66853

Abstract

View Articletitled, The Finite Element Method for Retention System of Radioactive Material Transport Package

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Topics: Finite element methods , Radioactive substances , Transport packages , Accuracy and precision , Density , Finite element analysis , Regulations

The Comprehensive Evaluation for Nuclear Facility Decommissioning Scheme Based on AHP-DEA Method

Lu Bai, Yong-kuo Liu, Nan Chao

ICONE 2017; V004T06A021https://doi.org/10.1115/ICONE25-66906

Abstract

View Articletitled, The Comprehensive Evaluation for Nuclear Facility Decommissioning Scheme Based on AHP-DEA Method

PDF

Topics: Nuclear decommissioning , Construction , Decision making , Nuclear power stations , Optimization , Preferences , Radiation (Physics) , Safety

Penetration Jet Impingement Calculation in Engineering Application

Tong Wu, Ying Zhou, Tao Qi

ICONE 2017; V004T06A022https://doi.org/10.1115/ICONE25-67096

Abstract

View Articletitled, Penetration Jet Impingement Calculation in Engineering Application

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Topics: Drops , Engineering systems and industry applications , Enthalpy , Flashing , Floods , Flow (Dynamics) , Fluids , Hazard analysis , Hot water , Jets

Dependency Analysis of Critical Parameters Influencing the Reliability of Thermal-Hydraulic Nuclear Passive Systems

Samuel Abiodun Olatubosun, Zhijian Zhang

ICONE 2017; V004T06A023https://doi.org/10.1115/ICONE25-67116

Abstract

View Articletitled, Dependency Analysis of Critical Parameters Influencing the Reliability of Thermal-Hydraulic Nuclear Passive Systems

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Topics: Reliability , Boilers , Event history analysis , Nuclear reactors , Safety , Water

Experimental Study of Debris-Loading Head Loss Test for PWR Fuel Assembly After LOCA

Da Wang, Fenglei Niu, Weiqian Zhuo, Jingwen Ren, Zhangpeng Guo, Hammad Aslam Bhatti

ICONE 2017; V004T06A024https://doi.org/10.1115/ICONE25-67185

Abstract

View Articletitled, Experimental Study of Debris-Loading Head Loss Test for PWR Fuel Assembly After LOCA

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Topics: Fuels , Manufacturing , Pressurized water reactors , Pressure drop , Accidents , Containment , Coolants , Cooling , Flow (Dynamics) , Safety

Conceptual Design of an Ex-Vessel Melt Cooling Device

Li Zhang, Mingrui Yu, Qiang Guo, Yiming Zhu, Yidan Yuan, Weimin Ma

ICONE 2017; V004T06A025https://doi.org/10.1115/ICONE25-67190

Abstract

View Articletitled, Conceptual Design of an Ex-Vessel Melt Cooling Device

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Topics: Conceptual design , Cooling , Vessels , Accidents , Cavities , Film boiling , Heat flux , Light water reactors , Pipes , Reactor vessels

Experimental Investigation on the Pipe Leakage

Benan Cai, Qi Zhang, Yu Weng, Hongfang Gu, Haijun Wang

ICONE 2017; V004T06A026https://doi.org/10.1115/ICONE25-67251

Abstract

View Articletitled, Experimental Investigation on the Pipe Leakage

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Topics: Leakage , Pipes , Temperature , Fracture (Materials) , Pipelines , Nuclear power stations , High temperature , Fatigue , Fluids , High pressure (Physics)

Planning the Selection and Assignment of Security Forensics Countermeasures

Edita Bajramovic, Jürgen Bochtler, Ines Ben Zid, Andreas Lainer

ICONE 2017; V004T06A027https://doi.org/10.1115/ICONE25-67328

Abstract

View Articletitled, Planning the Selection and Assignment of Security Forensics Countermeasures

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Topics: Countermeasures , Forensic sciences , Security , Computer security , Modeling , Engineering prototypes

Research and Development of Protective Action Analysis System for the Public Based on Operation Intervention Level in Reactor Accident

Xiaoxiao Xu, Jiangang Zhang, Yapeng Yang, Zongyang Feng, Linsheng Jia

ICONE 2017; V004T06A028https://doi.org/10.1115/ICONE25-67367

Abstract

View Articletitled, Research and Development of Protective Action Analysis System for the Public Based on Operation Intervention Level in Reactor Accident

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Topics: Accidents , Industrial research , Protective actions , Databases , Decision making , Internet , Meteorology , Nuclear power stations , Vehicles

Development, Distribution and Maintenance of Application Security Controls for Nuclear

Karl Waedt, Yongjian Ding, Antonio Ciriello, Xinxin Lou

ICONE 2017; V004T06A029https://doi.org/10.1115/ICONE25-67499

Abstract

View Articletitled, Development, Distribution and Maintenance of Application Security Controls for Nuclear

PDF

Topics: Maintenance , Security , Computer security , Countermeasures , Teams , Engineering standards , National Institute of Standards and Technology , Risk , Safety

Experimental Study of Performance of Cold Crucible Induction Melter in Melting Corium Simulant

Caixin Sun, Ying Chen, Lian Chen, Huajian Chang, Jie Pei, Fang Tian, Xinchen Xu

ICONE 2017; V004T06A030https://doi.org/10.1115/ICONE25-67527

Abstract

View Articletitled, Experimental Study of Performance of Cold Crucible Induction Melter in Melting Corium Simulant

PDF

Topics: Electromagnetic induction , Melting , Heating , Zirconium , Cooling , Temperature , Water , Circuits , Copper , Design

Analysis of Cyber Security Incident in South Korean Nuclear Power Plant and Cyber Security Solutions for Nuclear Power Industrial Control System

Yufang Bian, Jing Li, Baojuan Yin

ICONE 2017; V004T06A031https://doi.org/10.1115/ICONE25-67577

Abstract

View Articletitled, Analysis of Cyber Security Incident in South Korean Nuclear Power Plant and Cyber Security Solutions for Nuclear Power Industrial Control System

PDF

Topics: Computer security , Industrial controls , Nuclear power , Nuclear power stations , Internet , Leakage , Security

Study on Emergency Action Levels of the Modular High Temperature Gas-Cooled Reactor

Xiaochuan Zang, Tao Liu

ICONE 2017; V004T06A032https://doi.org/10.1115/ICONE25-67583

Abstract

View Articletitled, Study on Emergency Action Levels of the Modular High Temperature Gas-Cooled Reactor

PDF

Topics: Emergencies , Very high temperature reactors , Nuclear fission , Pressurized water reactors , Safety , Accidents , Design , Hazards

Melting Simulation Using a Particle Method With Angular Momentum Conservation

Masahiro Kondo, Shota Ueda, Koji Okamoto

ICONE 2017; V004T06A033https://doi.org/10.1115/ICONE25-67588

Abstract

View Articletitled, Melting Simulation Using a Particle Method With Angular Momentum Conservation

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Topics: Angular momentum , Melting , Particulate matter , Simulation , Geometry , Accidents , Cantilevers , Dams , Nuclear power stations , Solidification

Biaxial-EDC Test Attempts With Pre-Cracked Zircaloy-4 Cladding Tubes

Feng Li, Takeshi Mihara, Yutaka Udagawa, Masaki Amaya

ICONE 2017; V004T06A034https://doi.org/10.1115/ICONE25-67602

Abstract

View Articletitled, Biaxial-EDC Test Attempts With Pre-Cracked Zircaloy-4 Cladding Tubes

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Topics: Cladding systems (Building) , Failure , Fracture (Materials) , Fuels , Stress , Accidents , Bonding , Compression , Crack propagation , Deformation

High Temperature Oxidation of Zry-4 in Oxygen-Nitrogen Atmospheres

Martin Negyesi, Masaki Amaya

ICONE 2017; V004T06A035https://doi.org/10.1115/ICONE25-67609

Abstract

View Articletitled, High Temperature Oxidation of Zry-4 in Oxygen-Nitrogen Atmospheres

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Topics: High temperature , Nitrogen , Oxidation , Oxygen , Weight (Mass) , Flow (Dynamics) , Cladding systems (Building) , Compression , Embrittlement , Fuels

Crack Growth Safety Assessment of Overlay Weld on the Ω Seal for Control Rod Drive Mechanism

Jiacheng Luo, Yong Zhang, Pengzhou Li, Juan Luo, Lei Sun

ICONE 2017; V004T06A036https://doi.org/10.1115/ICONE25-67615

Abstract

View Articletitled, Crack Growth Safety Assessment of Overlay Weld on the Ω Seal for Control Rod Drive Mechanism

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Topics: Fracture (Materials) , Overlays (Materials engineering) , Safety , Pressure , Stress corrosion cracking , Computational methods , Coolants , Cycles , Design , Fatigue

Passive System Reliability Analysis Based on Improved Support Vector Machine

Hao Ding, Qi Cai, Yongfa Zhang, Lizhi Jiang

ICONE 2017; V004T06A037https://doi.org/10.1115/ICONE25-67621

Abstract

View Articletitled, Passive System Reliability Analysis Based on Improved Support Vector Machine

PDF

Topics: Event history analysis , Support vector machines , Failure , Approximation , Artificial neural networks , Failure mechanisms , Nuclear reactors , Polynomials , Probability , Reliability

Assessment on Direct Debris Interaction at High Pressure Melt Ejection Scenario in Level 2 PSA

Naoki Hirokawa, Hiromasa Chitose, Kohei Hisamochi

ICONE 2017; V004T06A038https://doi.org/10.1115/ICONE25-67635

Abstract

View Articletitled, Assessment on Direct Debris Interaction at High Pressure Melt Ejection Scenario in Level 2 PSA

PDF

Topics: Accidents , Boiling water reactors , Containment , Damage , Emergency core cooling systems , Failure , Heating , High pressure (Physics) , Particulate matter , Probabilistic safety assessment

Pressure Drops and Model Modification for Two-Phase Flow in Porous Beds With Coarse Particles

Xumao Zou, Liangxing Li, Liubo Kong, Huasheng Wang

ICONE 2017; V004T06A039https://doi.org/10.1115/ICONE25-67645

Abstract

View Articletitled, Pressure Drops and Model Modification for Two-Phase Flow in Porous Beds With Coarse Particles

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Topics: Particulate matter , Pressure drop , Two-phase flow , Drag (Fluid dynamics) , Flow (Dynamics) , Fluids , Reliability , Temperature , Test facilities , Uncertainty

Numerical and Experimental Investigation on Influence Factors of the Leakage Rate for a Large-Size Pressure Gate With Rubber O-Ring Sealing Structure

Huang Hao, Huang Xiaoming, Xu Guoliang, Fang Lin, Shi Chunyu, Sun Jiawei, Lv Xiangkui

ICONE 2017; V004T06A040https://doi.org/10.1115/ICONE25-67735

Abstract

View Articletitled, Numerical and Experimental Investigation on Influence Factors of the Leakage Rate for a Large-Size Pressure Gate With Rubber O-Ring Sealing Structure

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Topics: Gates (Closures) , Leakage , Pressure , Rubber , Sealing (Process) , Seals , Finite element methods , Accidents , Design , Mechanical behavior

A New Effective Numerical Method for Leakage Rate Prediction of the Metal Gasket Sealing Assembly

Fang Lin, Xu Guoliang, Xiaoming Huang, Huang Hao, Du Yang, Zhu Yiping, Yang Wenjian

ICONE 2017; V004T06A041https://doi.org/10.1115/ICONE25-67739

Abstract

View Articletitled, A New Effective Numerical Method for Leakage Rate Prediction of the Metal Gasket Sealing Assembly

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Topics: Gaskets , Leakage , Manufacturing , Metals , Numerical analysis , Sealing (Process) , Surface roughness , Separation (Technology) , Deformation , Channel flow

Minimum Dose Path Planning in Complex Radioactive Environments With Sampling-Based Algorithms

Nan Chao, Yong-kuo Liu, Hong Xia, Lu Bai

ICONE 2017; V004T06A042https://doi.org/10.1115/ICONE25-67749

Abstract

View Articletitled, Minimum Dose Path Planning in Complex Radioactive Environments With Sampling-Based Algorithms

PDF

Topics: Algorithms , Path planning , Navigation , Radiation (Physics) , Safety , Simulation results , Virtual reality

Reconstruction of Core Overheating Damage Fraction Based on Neural Network Method

Wenjing Li, Xiaoming Yang, Xinlu Yu

ICONE 2017; V004T06A043https://doi.org/10.1115/ICONE25-67840

Abstract

View Articletitled, Reconstruction of Core Overheating Damage Fraction Based on Neural Network Method

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Topics: Artificial neural networks , Damage , Damage assessment , Neural network models , Nuclear power stations , Containment , Emergency response , Errors , Hydrogen , Pressure

Report on Feasibility Study for Radiation Alarming Data Collection From Containers at Laem Cha Bang International Sea Port, Thailand

Sunchai Nilsuwankosit

ICONE 2017; V004T06A044https://doi.org/10.1115/ICONE25-67908

Abstract

View Articletitled, Report on Feasibility Study for Radiation Alarming Data Collection From Containers at Laem Cha Bang International Sea Port, Thailand

PDF

Topics: Containers , Data collection , Radiation (Physics) , Seas , Ceramics , Contamination , Fertilizers , Metals , Minerals , Plastics

Data Flow Based Cyber Security Defense-in-Depth Model of I&C System for Nuclear Power Plants

Bing Hu, Longqiang Zhang, Zhiwu Guo, Youran Li, Wei Sun, Liang Zhou, Yong Tian

ICONE 2017; V004T06A045https://doi.org/10.1115/ICONE25-67918

Abstract

View Articletitled, Data Flow Based Cyber Security Defense-in-Depth Model of I&C System for Nuclear Power Plants

PDF

Topics: Computer security , Defense industry , Flow (Dynamics) , Nuclear power stations , Instrumentation , Network models , Regulations

Probabilistic Assessment of Countermeasures for Loss of Ultimate Heat Sink to Spent Fuel Pool

Bumpei Fujioka, Naoki Hirokawa, Daisuke Taniguchi

ICONE 2017; V004T06A046https://doi.org/10.1115/ICONE25-67999

Abstract

View Articletitled, Probabilistic Assessment of Countermeasures for Loss of Ultimate Heat Sink to Spent Fuel Pool

PDF

Topics: Countermeasures , Heat sinks , Spent nuclear fuels , Accidents , Cooling , Damage , Earthquakes , Fuels , Fukushima nuclear disaster, Japan, 2011 , Nuclear power stations

Sensitivity Analysis on the Detailed Plant Operational State for Shutdown PSA

Daichi Shiota, Naoki Hirokawa, Kohei Hisamochi

ICONE 2017; V004T06A047https://doi.org/10.1115/ICONE25-68007

Abstract

View Articletitled, Sensitivity Analysis on the Detailed Plant Operational State for Shutdown PSA

PDF

Topics: Sensitivity analysis , Boiling water reactors , Accidents , Containment vessels , Coolants , Inspection , Maintenance , Modeling , Nuclear power stations , Pressure

Risk Management

Research and Development of CRAMTRA 1.0 Code for Consequence Assessment From Radioactive Material Transport

Wang Renze, Zhang Jiangang, Li Guoqiang, Zhuang Dajie, Sun Hongchao, Wang Xuexin, Meng Dongyuan, Sun Shutang

ICONE 2017; V004T14A001https://doi.org/10.1115/ICONE25-66011

Abstract

View Articletitled, Research and Development of CRAMTRA 1.0 Code for Consequence Assessment From Radioactive Material Transport

PDF

Topics: Industrial research , Radioactive substances , China , Computer programming , Design , Intellectual property

PSA Research of Transport of New Fuel of HTR-PM

Wang Renze, Zhang Jiangang, Li Guoqiang, Zhuang Dajie, Meng Dongyuan, Wang Xuexin, Sun Hongchao, Sun Shutang

ICONE 2017; V004T14A002https://doi.org/10.1115/ICONE25-66012

Abstract

View Articletitled, PSA Research of Transport of New Fuel of HTR-PM

PDF

Topics: Fuels , Accidents , Radiation (Physics) , Hoists , Risk , Risk assessment , Emergencies , High temperature , Probabilistic safety assessment , Radioactive substances

Recommendations for Conducting Probabilistic Risk Assessment of Spent Fuel Storage Facilities

Sai Zhang, Jun Zhao, Jiejuan Tong, Zhixin Xu

ICONE 2017; V004T14A003https://doi.org/10.1115/ICONE25-66023

Abstract

View Articletitled, Recommendations for Conducting Probabilistic Risk Assessment of Spent Fuel Storage Facilities

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Topics: Probabilistic risk assessment , Spent fuel storage , Storage , Risk , Fuels , Nuclear power stations , Accidents , Safety , Fukushima nuclear disaster, Japan, 2011 , Heat

PSA Application in the Diverse Actuation System Design

Zhan Wenhui, Zhang Binbin

ICONE 2017; V004T14A004https://doi.org/10.1115/ICONE25-66044

Abstract

View Articletitled, PSA Application in the Diverse Actuation System Design

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Topics: Design , Data acquisition systems , Safety , Accidents , Damage , Monitoring systems , Nuclear power stations , Probabilistic safety assessment , Signals

Development of Probabilistic Risk Assessment Methodology of Decay Heat Removal Function Against Combination Hazards of Strong Wind and Rainfall for Sodium-Cooled Fast Reactors

Hidemasa Yamano, Hiroyuki Nishino, Kenichi Kurisaka

ICONE 2017; V004T14A005https://doi.org/10.1115/ICONE25-66059

Abstract

View Articletitled, Development of Probabilistic Risk Assessment Methodology of Decay Heat Removal Function Against Combination Hazards of Strong Wind and Rainfall for Sodium-Cooled Fast Reactors

PDF

Topics: Hazards , Heat , Probabilistic risk assessment , Sodium fast reactors , Wind , Failure , Missiles , Cooling systems , Drops , Wind velocity

Research and Application to Risk-Informed NPP Events Trend Analysis Method

Chen Shijun, Zhang Sifan, Chen Peifeng, Zhang Kuan

ICONE 2017; V004T14A006https://doi.org/10.1115/ICONE25-66117

Abstract

View Articletitled, Research and Application to Risk-Informed NPP Events Trend Analysis Method

PDF

Topics: Nuclear power stations , Risk , Trend analysis , Corrective actions , Event history analysis , Probabilistic safety assessment , Safety , Statistics , Weight (Mass)

Preliminary Study on Risk-Informed LBLOCA of CPR1000

Jianyang Song, Jingquan Liu, Ting Wang, Pingping Liu, Zhikang Lin

ICONE 2017; V004T14A007https://doi.org/10.1115/ICONE25-66201

Abstract

View Articletitled, Preliminary Study on Risk-Informed LBLOCA of CPR1000

PDF

Topics: Risk , Nuclear power stations , Probabilistic safety assessment , Probability , Safety , Stress

Development of a Sea-State Database in the Northwest Pacific Ocean by Long-Term Numerical Hindcast Modelling

Jian Shi, Antoine Joly, Jinhai Zheng, Jisheng Zhang, Tian Chen, Guofei Chen

ICONE 2017; V004T14A008https://doi.org/10.1115/ICONE25-66281

Abstract

View Articletitled, Development of a Sea-State Database in the Northwest Pacific Ocean by Long-Term Numerical Hindcast Modelling

PDF

Topics: Databases , Modeling , Pacific Ocean , Seas , Significant wave heights , Waves , Shorelines , Buoys , Nuclear power stations , Calibration

The Shutdown PSA Model of the TQNPP CANDU Reactor and the Outage Risk Management

Xiaochun Peng, Qiang Fu, Yu Han, Yong Cao

ICONE 2017; V004T14A009https://doi.org/10.1115/ICONE25-66295

Abstract

View Articletitled, The Shutdown PSA Model of the TQNPP CANDU Reactor and the Outage Risk Management

PDF

Topics: Risk , Risk assessment , Risk management , Safety

Fault Tree Analysis Based on Dynamic Uncertain Causality Graph

Zhenxu Zhou, Qin Zhang

ICONE 2017; V004T14A010https://doi.org/10.1115/ICONE25-66296

Abstract

View Articletitled, Fault Tree Analysis Based on Dynamic Uncertain Causality Graph

PDF

Topics: Algorithms , Cycles , Failure , Fourier transform spectroscopy , Modeling , Nuclear power stations , Weapons

Risk Analysis of Water Intake Structure Blockage in a Nuclear Power Plant

Jinkai Wang, Feng Duan

ICONE 2017; V004T14A011https://doi.org/10.1115/ICONE25-66363

Abstract

View Articletitled, Risk Analysis of Water Intake Structure Blockage in a Nuclear Power Plant

PDF

Topics: Nuclear power stations , Risk analysis , Water , Risk , Safety , Nuclear power plant operations , Sands , Sedimentation

Hydrogen Concentration Measuring System Designed for Severe Accidents in Containment

Sha Luo, Yunkai Qian, Mingjun Ren, Liang Qin, Xu Wang

ICONE 2017; V004T14A012https://doi.org/10.1115/ICONE25-66375

Abstract

View Articletitled, Hydrogen Concentration Measuring System Designed for Severe Accidents in Containment

PDF

Topics: Accidents , Containment , Hydrogen , Sensors , Temperature , Catalysts , Earthquakes , Heat , Irradiation (Radiation exposure) , Pressure

A Modeling Method of the Branch Probability of the Temperature-Induced SGTR Phenomenon

Zibin Liu, Dingqing Guo, Bing Zhang, Jinkai Wang

ICONE 2017; V004T14A013https://doi.org/10.1115/ICONE25-66378

Abstract

View Articletitled, A Modeling Method of the Branch Probability of the Temperature-Induced SGTR Phenomenon

PDF

Topics: Modeling , Probability , Temperature , Accidents , Boilers , Containment , Nuclear power stations , Radioactive substances , Rupture

Performance and Application of Internal Flood Probabilistic Safety Assessment in Nuclear Power Plant Design

Lihua Huang, Xiang Liu, Lijuan Wang

ICONE 2017; V004T14A014https://doi.org/10.1115/ICONE25-66398

Abstract

View Articletitled, Performance and Application of Internal Flood Probabilistic Safety Assessment in Nuclear Power Plant Design

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Topics: Floods , Nuclear design , Probabilistic safety assessment , Nuclear power stations , Design , Risk

Research of the Node Ordering Technique According to the Shortest Fault Tree

Guofeng Tang, Jingyu Zhang, Wei Gao, Qinfang Zhang

ICONE 2017; V004T14A015https://doi.org/10.1115/ICONE25-66436

Abstract

View Articletitled, Research of the Node Ordering Technique According to the Shortest Fault Tree

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Topics: Algorithms , Engines , Probabilistic safety assessment

Research of the Minimal Cut Sets Post Processing of the PSA Quantification Engine

Guofeng Tang, Wei Gao

ICONE 2017; V004T14A016https://doi.org/10.1115/ICONE25-66442

Abstract

View Articletitled, Research of the Minimal Cut Sets Post Processing of the PSA Quantification Engine

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Topics: Algorithms , Engines , Probabilistic safety assessment

The Application of Fault Tree Method in Systematic Multiple Spurious Operation Analysis in Fire PSA

Hu Yuehua, Li Lin, Yan Zhen, Song Lei

ICONE 2017; V004T14A017https://doi.org/10.1115/ICONE25-66454

Abstract

View Articletitled, The Application of Fault Tree Method in Systematic Multiple Spurious Operation Analysis in Fire PSA

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Topics: Fire , Modeling , Nuclear reactor coolants , Risk , Transfer functions

Seismic Risk Analysis of the 380VAC Emergency Electrical Power Distribution Cabinets of a Nuclear Power Plant in China

Jianfeng Yang, Handing Wang, Xiaoming Zhang, Bingchen Feng, Weijin Wang, Zhao Wang

ICONE 2017; V004T14A018https://doi.org/10.1115/ICONE25-66548

Abstract

View Articletitled, Seismic Risk Analysis of the 380VAC Emergency Electrical Power Distribution Cabinets of a Nuclear Power Plant in China

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Topics: China , Earthquake risk , Electricity (Physics) , Emergencies , Nuclear power stations , Failure , Earthquakes , Chatter , Computer software , Probability

Reliability Assessment of Reactor AP1000 Passive ERVC System

Cui Chengxin, Huang Ting, Chen Lian, Chen Ying, Zhang Lei

ICONE 2017; V004T14A019https://doi.org/10.1115/ICONE25-66633

Abstract

View Articletitled, Reliability Assessment of Reactor AP1000 Passive ERVC System

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Topics: Reliability , Nuclear power stations , Reactor vessels , Safety , Cooling , Density , Design , Temperature , Thermal hydraulics

Development and Application of CAP1400 Probabilistic Safety Assessment

Qinfang Zhang, Wenhui Zhan, Yongping Qiu, Zhaohua Li, Jiandong He

ICONE 2017; V004T14A020https://doi.org/10.1115/ICONE25-66651

Abstract

View Articletitled, Development and Application of CAP1400 Probabilistic Safety Assessment

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Topics: Probabilistic safety assessment , Design , Fire , Floods , Control systems , Cooling systems , Instrumentation , Valves , Vessels

An Advanced Method for Evaluating Risk From Seismically-Induced Internal Fires and Floods

Paul J. Amico, Pierre Macheret, Robert P. Kassawara

ICONE 2017; V004T14A021https://doi.org/10.1115/ICONE25-66721

Abstract

View Articletitled, An Advanced Method for Evaluating Risk From Seismically-Induced Internal Fires and Floods

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Topics: Fire , Floods , Risk , Hazards , Safety , Earthquakes , Nuclear power stations , Probabilistic safety assessment , Transients (Dynamics)

A Hybrid Approach to Seismic and Other External Hazards HRA: More Efficient and More Realistic

Paul Amico, Erin Collins, Elizabeth Cook

ICONE 2017; V004T14A022https://doi.org/10.1115/ICONE25-66724

Abstract

View Articletitled, A Hybrid Approach to Seismic and Other External Hazards HRA: More Efficient and More Realistic

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Topics: Hazards , Human reliability analysis , Damage , Fire , Probabilistic risk assessment

Study on the Technical Method of Level 2 Probabilistic Safety Assessment in Multiple External Hazards Compound Situations

Liu Wei-dong, Dai Hong-wei, Peng Peng-yi, Zhang Ze-feng, Wang En-qi

ICONE 2017; V004T14A023https://doi.org/10.1115/ICONE25-66752

Abstract

View Articletitled, Study on the Technical Method of Level 2 Probabilistic Safety Assessment in Multiple External Hazards Compound Situations

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Topics: Hazards , Probabilistic safety assessment , Nuclear power stations , Risk , Radioisotopes , Safety

Study on Risk Analysis and Mitigation Measures for Total Loss of Heat Sink Accident in a Nuclear Power Plant

Liang Pei

ICONE 2017; V004T14A024https://doi.org/10.1115/ICONE25-66830

Abstract

View Articletitled, Study on Risk Analysis and Mitigation Measures for Total Loss of Heat Sink Accident in a Nuclear Power Plant

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Topics: Accidents , Heat sinks , Nuclear power stations , Risk analysis , Risk , Pressurized water reactors , China , Probabilistic safety assessment , Safety , Water

The Experimental Study on Stratification and Transport of Hydrogen in the Containment With Light Non-Condensable Gas

Xiaobo Lee, Xuefeng Lyu, Ke Ji

ICONE 2017; V004T14A025https://doi.org/10.1115/ICONE25-66833

Abstract

View Articletitled, The Experimental Study on Stratification and Transport of Hydrogen in the Containment With Light Non-Condensable Gas

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Topics: Containment , Hydrogen , Domes (Structural elements) , Helium , Sprays , Buoyancy , China , Containers , Drops , Electricity (Physics)

The Application of Risk-Informed Decision-Making Approach in Optimization of Allowed Outage Time for Safety System in Nuclear Power Plant

Licun Wu, Chao Ma, Wei Deng

ICONE 2017; V004T14A026https://doi.org/10.1115/ICONE25-66926

Abstract

View Articletitled, The Application of Risk-Informed Decision-Making Approach in Optimization of Allowed Outage Time for Safety System in Nuclear Power Plant

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Topics: Nuclear power stations , Optimization , Risk-based decision making , Safety , Maintenance , High pressure (Physics) , Risk

A Study on Maintenance Rule Application in VVER NPP

Ma Chao, Deng Wei, An Jin

ICONE 2017; V004T14A027https://doi.org/10.1115/ICONE25-66929

Abstract

View Articletitled, A Study on Maintenance Rule Application in VVER NPP

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Topics: Maintenance , Nuclear power stations , China , Energy generation , Probabilistic risk assessment , Public utilities , Safety

Research and Software Implementation of Seismic Probabilistic Safety Analysis Quantification Method

Wei Gao, Guofeng Tang, Jingyu Zhang, Qinfang Zhang

ICONE 2017; V004T14A028https://doi.org/10.1115/ICONE25-66973

Abstract

View Articletitled, Research and Software Implementation of Seismic Probabilistic Safety Analysis Quantification Method

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Topics: Computer software , Probabilistic safety assessment , Algorithms , Earthquake risk , Nuclear power stations , Fukushima nuclear disaster, Japan, 2011 , Monte Carlo methods , Probability

Methodology and Application of Human Reliability Analysis in CAP1400 Nuclear Power Plant

Yongping Qiu, Jiandong He, Juntao Hu, Yucheng Zhuo, Jie He

ICONE 2017; V004T14A029https://doi.org/10.1115/ICONE25-66974

Abstract

View Articletitled, Methodology and Application of Human Reliability Analysis in CAP1400 Nuclear Power Plant

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Topics: Human reliability analysis , Nuclear power stations , Human factors , Safety , Engineering design , Failure , Fire , Floods , Probabilistic safety assessment

Study on Social Stability Risk Analysis for Nuclear Power Projects

Zhu Rongxu, Zhao Feng, Wang Haifeng

ICONE 2017; V004T14A030https://doi.org/10.1115/ICONE25-66978

Abstract

View Articletitled, Study on Social Stability Risk Analysis for Nuclear Power Projects

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Topics: Nuclear power , Risk analysis , Stability , Construction , Nuclear power stations , Risk , Risk assessment , Risk mitigation

Probabilistic Safety Assessment for CAP Nuclear Power Plant Spent Fuel Pool

Xu Yiquan, Zhuo Yucheng, Yang Yajun, Fu Hao

ICONE 2017; V004T14A031https://doi.org/10.1115/ICONE25-66979

Abstract

View Articletitled, Probabilistic Safety Assessment for CAP Nuclear Power Plant Spent Fuel Pool

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Topics: Nuclear power stations , Probabilistic safety assessment , Spent nuclear fuels , Damage , Pressurized water reactors , Risk , Safety , Accidents , China , Computer software

Seismic Margin Assessment and Improvements of Qinshan Nuclear Power Plant

Leilei Xu, Xiaoling Zhao, Zhaohua Li

ICONE 2017; V004T14A032https://doi.org/10.1115/ICONE25-66983

Abstract

View Articletitled, Seismic Margin Assessment and Improvements of Qinshan Nuclear Power Plant

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Topics: Nuclear power stations , Safety , Design , Nuclear engineering , China , Fukushima nuclear disaster, Japan, 2011 , Nuclear industry , Nuclear power

Application of Internal Fire PRA in Elimination of Fire Common Modes

Xiang Liu, Lihua Huang, Zeyu Liu

ICONE 2017; V004T14A033https://doi.org/10.1115/ICONE25-67033

Abstract

View Articletitled, Application of Internal Fire PRA in Elimination of Fire Common Modes

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Topics: Fire , Design , Nuclear power stations , Safety , Cables , Coating processes , Coatings , Construction , Pumps , Risk

Research on the Inspection Strategy Change Based on Risk-Informed Method in Nuclear Power Plant

Ye Shuixiang, Li Qiongzhe, Xi Haiying

ICONE 2017; V004T14A034https://doi.org/10.1115/ICONE25-67173

Abstract

View Articletitled, Research on the Inspection Strategy Change Based on Risk-Informed Method in Nuclear Power Plant

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Topics: Inspection , Nuclear power stations , Risk , Heat exchangers , Optimization , Risk-based decision making

Application of Probabilistic Safety Assessment in the Design of Instrumentation and Control Systems for Nuclear Power Plants

Pengyi Peng, Weidong Liu, Zhichao Yang

ICONE 2017; V004T14A035https://doi.org/10.1115/ICONE25-67178

Abstract

View Articletitled, Application of Probabilistic Safety Assessment in the Design of Instrumentation and Control Systems for Nuclear Power Plants

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Topics: Control systems , Design , Instrumentation , Nuclear power stations , Probabilistic safety assessment , Safety , Risk , Economics , Redundancy (Engineering) , Risk assessment

An Improved Algorithm for Potential Accident Consequence Assessment at NPPs Based on PAVAN

Chen Qian, Zhai Liang, Yin Yuhao, Tao Yunliang

ICONE 2017; V004T14A036https://doi.org/10.1115/ICONE25-67262

Abstract

View Articletitled, An Improved Algorithm for Potential Accident Consequence Assessment at NPPs Based on PAVAN

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Topics: Accidents , Algorithms , Nuclear power stations , Meteorology , Probability , Curve fitting , China , Design , Pacific Ocean , Radioactive substances

Challenges of Evolution for the Risk-Informed Decision Making Standard

Yoshiyuki Narumiya, Kentaro Hayashi, Takahiro Kuramoto

ICONE 2017; V004T14A037https://doi.org/10.1115/ICONE25-67525

Abstract

View Articletitled, Challenges of Evolution for the Risk-Informed Decision Making Standard

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Topics: Risk-based decision making , Safety , Nuclear power stations , Risk , Decision making , Design , Nuclear power , Public utilities

Development of Probabilistic Risk Assessment Methodology of Decay Heat Removal Function Against Combination Hazard of Low Temperature and Snow for Sodium-Cooled Fast Reactors

Hiroyuki Nishino, Hidemasa Yamano, Kenichi Kurisaka

ICONE 2017; V004T14A038https://doi.org/10.1115/ICONE25-67627

Abstract

View Articletitled, Development of Probabilistic Risk Assessment Methodology of Decay Heat Removal Function Against Combination Hazard of Low Temperature and Snow for Sodium-Cooled Fast Reactors

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Topics: Hazards , Heat , Low temperature , Probabilistic risk assessment , Sodium fast reactors , Failure , Probability , Damage , Filters , Accidents

Research on Quantitative Safety Objectives of the Risk-Informed Management Activities in Nuclear Power Plants in China

Li Huwei, Yi Yan, Wang Chuang, Xiong Wenbin, Huang Zhichao, Chu Yongyue

ICONE 2017; V004T14A039https://doi.org/10.1115/ICONE25-67662

Abstract

View Articletitled, Research on Quantitative Safety Objectives of the Risk-Informed Management Activities in Nuclear Power Plants in China

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Topics: China , Nuclear power stations , Risk , Safety , Damage , Optimization , Risk analysis

A Study of Seismic Probability Safety Assessment for a Typical Three-Loop Pressurized Water Reactor Nuclear Power Plant

Yuqing Wang, Lingzhi Li, Dongmei Wang

ICONE 2017; V004T14A040https://doi.org/10.1115/ICONE25-67793

Abstract

View Articletitled, A Study of Seismic Probability Safety Assessment for a Typical Three-Loop Pressurized Water Reactor Nuclear Power Plant

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Topics: Nuclear power stations , Pressurized water reactors , Probability , Safety , Earthquake risk , Earthquakes , Accidents , Alternating current (Electricity) , Ceilings , Computer software

Risk Analysis of Spent Fuel Pool Caused by Seismic Events

Ming Wang, Modi Lin, Jinkai Wang, Chunju Yang

ICONE 2017; V004T14A041https://doi.org/10.1115/ICONE25-67867

Abstract

View Articletitled, Risk Analysis of Spent Fuel Pool Caused by Seismic Events

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Topics: Earthquakes , Risk analysis , Spent nuclear fuels , Accidents , Fuels , Damage , Design , Risk , Collapse , Probability

Sneak Circuit Analysis of Chemical and Volume Control System

Gong Zili, Liao Yi, Chen Lei, Wang Cong

ICONE 2017; V004T14A042https://doi.org/10.1115/ICONE25-67894

Abstract

View Articletitled, Sneak Circuit Analysis of Chemical and Volume Control System

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Topics: Circuits , Control systems , Design , Nuclear power stations , Patents , Pipelines , Pressure , Risk , Stability , Valves

Code Developing of Fragility Analysis Program for Seismic Safety Evaluation of Nuclear Power Plant

Zhao Wang, Jianfeng Yang, Weijin Wang, Bingchen Feng, Xiaoming Zhang

ICONE 2017; V004T14A043https://doi.org/10.1115/ICONE25-67912

Abstract

View Articletitled, Code Developing of Fragility Analysis Program for Seismic Safety Evaluation of Nuclear Power Plant

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Topics: Nuclear power stations , Safety , Failure , Uncertainty , Probability , Earthquakes , Monte Carlo methods , Accidents , Computational methods , Earthquake risk

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