Proceedings Papers

Select Year

Select Conference

Select Volume

Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs

Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant

The Effects of Compressibility and Piping Geometry on Steamhammer Loads

Frederick J. Moody, Robert Stakenborghs

ICONE 2018; V001T01A001https://doi.org/10.1115/ICONE26-81003

Abstract

View Articletitled, The Effects of Compressibility and Piping Geometry on Steamhammer Loads

PDF

Topics: Compressibility , Geometry , Pipes , Stress , Flow (Dynamics) , Valves , Turbines , ASME Standards , Fluids , Nuclear power stations

Reliability Evaluation for Steam Generator in a Sodium-Cooled Fast Reactor

Huang Yi, Zhang Tian-yi, Wang Jun, Yuan Yu-chen, Dong Xin

ICONE 2018; V001T01A002https://doi.org/10.1115/ICONE26-81183

Abstract

View Articletitled, Reliability Evaluation for Steam Generator in a Sodium-Cooled Fast Reactor

PDF

Topics: Boilers , Reliability , Sodium fast reactors , Failure mechanisms , Design , Fast neutron reactors , Event history analysis , Failure , Failure mode and effects analysis , Filters

Study on Advanced PWR NPP Safety Related Equipment Qualification Function Requirement Design Methodology

Xu Zhao, Miao Zhuang, Yi Ke

ICONE 2018; V001T01A003https://doi.org/10.1115/ICONE26-81212

Abstract

View Articletitled, Study on Advanced PWR NPP Safety Related Equipment Qualification Function Requirement Design Methodology

PDF

Topics: Design methodology , Equipment qualification , Nuclear power stations , Pressurized water reactors , Safety , Design , China , Instrumentation , Intellectual property , Reliability

Classification Optimization for Waste Related Buildings and Structures of NPPs

Zongwen Hu, Yijie Qian, Li Fan

ICONE 2018; V001T01A004https://doi.org/10.1115/ICONE26-81408

Abstract

View Articletitled, Classification Optimization for Waste Related Buildings and Structures of NPPs

PDF

Topics: Nuclear power stations , Optimization , Structures , Nuclear power , Economics , Radioactive wastes , Regulations

Study on NPP Reactivity Accident Operating Strategy Design Based on Function Analysis and Task Analysis Technology

Yu Aimin, Xu Zhao, Du Yu, Sun Qian

ICONE 2018; V001T01A005https://doi.org/10.1115/ICONE26-81478

Abstract

View Articletitled, Study on NPP Reactivity Accident Operating Strategy Design Based on Function Analysis and Task Analysis Technology

PDF

Topics: Accidents , Design , Nuclear power stations , Task analysis , Defense industry , Design methodology

Study on the Operating Strategy Optimization of Moving to Remote Shutdown Station When Main Control Room Is Un-Inhabitable

Li Li, Zhang Shengtao, Xu Zhao, Du Yu

ICONE 2018; V001T01A006https://doi.org/10.1115/ICONE26-81480

Abstract

View Articletitled, Study on the Operating Strategy Optimization of Moving to Remote Shutdown Station When Main Control Room Is Un-Inhabitable

PDF

Topics: Control rooms , Optimization , Nuclear power stations , Pressurized water reactors , Safety , Economics , Fire , Hardware , Heat , Nuclear reactor coolants

Residual Unbalanced Mass Determination of an AMBs Controlled Rotor Based on Control Current Analysis of the Feedback Loop

Tianpeng Fan, Zhe Sun, Xiaoshen Zhang, Xunshi Yan, Jingjing Zhao, Zhengang Shi

ICONE 2018; V001T01A007https://doi.org/10.1115/ICONE26-81575

Abstract

View Articletitled, Residual Unbalanced Mass Determination of an AMBs Controlled Rotor Based on Control Current Analysis of the Feedback Loop

PDF

Topics: Feedback , Rotors , Frequency response , Magnetic bearings , Security

Pump Bearing Fault Detection Based on EMD and SVM

Yi Feng, Xianling Li, Zhiwu Ke, Zhaoxu Chen, Mo Tao

ICONE 2018; V001T01A008https://doi.org/10.1115/ICONE26-81584

Abstract

View Articletitled, Pump Bearing Fault Detection Based on EMD and SVM

PDF

Topics: Bearings , Flaw detection , Pumps , Support vector machines , Signals , Coolants , Failure , Flow (Dynamics) , Fluids , Heat transfer

Calculational-Experimental Monitoring of Radiation Damage Parameters on VVER Equipment and Their Application During Equipment Residual Life-Time Estimation

Pavel Borodkin, Azamat Gazetdinov, Nikolay Khrennikov

ICONE 2018; V001T01A009https://doi.org/10.1115/ICONE26-81708

Abstract

View Articletitled, Calculational-Experimental Monitoring of Radiation Damage Parameters on VVER Equipment and Their Application During Equipment Residual Life-Time Estimation

PDF

Topics: Damage , Embrittlement , Fluence (Radiation measurement) , Metals , Neutrons , Nuclear power stations , Radiation (Physics) , Radiation damage , Reactor vessels , Reliability

Characteristic Tests on Transition Core of HTR-10

Liqiang Wei, Dongmei Ding, Ling Liu, Yucheng Wang, Xiaoming Chen, Feng Xie

ICONE 2018; V001T01A010https://doi.org/10.1115/ICONE26-81797

Abstract

View Articletitled, Characteristic Tests on Transition Core of HTR-10

PDF

Topics: Boron , Design , Helium , High temperature , Safety

The Influence of Centrifugal Pump Characteristics on Dynamic Loadings on Pipelines After Power Failure

Jerzy Marcinkiewicz, Krzysztof Karaskiewicz, Claes Joheman

ICONE 2018; V001T01A011https://doi.org/10.1115/ICONE26-81825

Abstract

View Articletitled, The Influence of Centrifugal Pump Characteristics on Dynamic Loadings on Pipelines After Power Failure

PDF

Topics: Centrifugal pumps , Failure , Pipelines , Pumps , Interpolation , Design , Flow (Dynamics) , Pipes , Piping systems , Stress

Transient Reactor Test Facility Restart 23 Years Later

Bradley K. Heath, Cody C. Race, Lee O. Nelson

ICONE 2018; V001T01A012https://doi.org/10.1115/ICONE26-81833

Abstract

View Articletitled, Transient Reactor Test Facility Restart 23 Years Later

PDF

Topics: Test facilities , Transients (Dynamics) , Testing , Safety , Nuclear reactors , Corrective actions , Inspection , Maintenance

Research on Gamma Camera Imaging Characteristics

Quanhu Zhang, Wenming Zuo, Sufen Li, Suxia Hou, Lin Zhuang, Wenheng Zhou

ICONE 2018; V001T01A013https://doi.org/10.1115/ICONE26-81936

Abstract

View Articletitled, Research on Gamma Camera Imaging Characteristics

PDF

Topics: Imaging , Emergencies , Radiation (Physics) , Radiation sources , Resolution (Optics)

A New Method of Integrating the RELAP5 to the RINSIM Simulation Platform

Chao Tan, Victor M. Quiroga, Zheng Fu, Zhengquan Xie

ICONE 2018; V001T01A014https://doi.org/10.1115/ICONE26-82016

Abstract

View Articletitled, A New Method of Integrating the RELAP5 to the RINSIM Simulation Platform

PDF

Topics: Simulation , Accuracy and precision , Pressurized water reactors , Stability , Transients (Dynamics)

On the Use of Robust Command Shaping for Vibration Reduction During Remote Handling of Large Components in Tokamak Devices

Stanislao Grazioso, Giuseppe Di Gironimo

ICONE 2018; V001T01A015https://doi.org/10.1115/ICONE26-82346

Abstract

View Articletitled, On the Use of Robust Command Shaping for Vibration Reduction During Remote Handling of Large Components in Tokamak Devices

PDF

Topics: Tokamaks , Vibration , Vessels , Engineering simulation , Simulation , Maintenance , Nuclear fusion , Shapes , Stress , Transients (Dynamics)

Virtual Prototyping and Simulation of Robotic Devices and Maintenance Procedures for Remote Handling Activities in the Access Cell of DONES

Stefano Papa, Giuseppe di Gironimo, Federica Casoria, Gioacchino Micciché

ICONE 2018; V001T01A016https://doi.org/10.1115/ICONE26-82390

Abstract

View Articletitled, Virtual Prototyping and Simulation of Robotic Devices and Maintenance Procedures for Remote Handling Activities in the Access Cell of DONES

PDF

Topics: Maintenance , Robotics , Simulation , Kinematics , Chain , Collaboration , Conceptual design , Cranes , Degrees of freedom , End effectors

Replacement of a Hot Cell Window at the Hot Fuel Examination Facility

Judith Carol Westphal, Ron Johansen, J. D. Kelly

ICONE 2018; V001T01A017https://doi.org/10.1115/ICONE26-82422

Abstract

View Articletitled, Replacement of a Hot Cell Window at the Hot Fuel Examination Facility

PDF

Topics: Fuels , Slabs , Leakage , Glass , Gaskets , Mineral oil , Design , Dust , Flanges , Adhesion

A Non-Contact Ultrasonic Sensor for General Corrosion Inspection of Thin Plates

Akinori Tamura, Masahiro Miki, Naoyuki Kono, Hiroshi Okazawa, Shinobu Okido, Chenghuan Zhong, Erik Fabre, Anthony J. Croxford, Paul D. Wilcox

ICONE 2018; V001T01A018https://doi.org/10.1115/ICONE26-82560

Abstract

View Articletitled, A Non-Contact Ultrasonic Sensor for General Corrosion Inspection of Thin Plates

PDF

Topics: Corrosion , Inspection , Plates (structures) , Ultrasonic transducers , Sensors , Engineering prototypes , Computer simulation , Air conditioning , Computer software , Ducts

Instrumentation and Control (I&C) and Influence of Human Factors

Design and Development of Virtual DCS Debugging and Research Platform Based on NPP Simulation Model

Caike Zhang, Jingwen Qi, Chun Liu, Chenglong Xie, Peibang Liu, Ming Qu

ICONE 2018; V001T04A001https://doi.org/10.1115/ICONE26-81122

Abstract

View Articletitled, Design and Development of Virtual DCS Debugging and Research Platform Based on NPP Simulation Model

PDF

Topics: Design , Nuclear power stations , Simulation models , China , Control systems , Machinery , Simulation , Testing

Design of Decoupled Mechanical Shim Control System for a Generation III+ Pressurized Water Reactor Based on Feedforward Compensation and Multimodel Approach

Pengfei Wang, Xinyu Wei, Fuyu Zhao

ICONE 2018; V001T04A002https://doi.org/10.1115/ICONE26-81142

Abstract

View Articletitled, Design of Decoupled Mechanical Shim Control System for a Generation III+ Pressurized Water Reactor Based on Feedforward Compensation and Multimodel Approach

PDF

Topics: Control systems , Design , Feedforward control , Pressurized water reactors , Control equipment , Temperature , Coolants , Stability , Stress , Transients (Dynamics)

Coordinated Control of a Small Pressurized Water Reactor

Peiwei Sun, Chong Wang

ICONE 2018; V001T04A003https://doi.org/10.1115/ICONE26-81156

Abstract

View Articletitled, Coordinated Control of a Small Pressurized Water Reactor

PDF

Topics: Pressurized water reactors , Coolants , Control systems , Boilers , Temperature , Water , Design , Engineering simulation , Feedwater , Flow (Dynamics)

Application of Virtual Reality Technology in Nuclear Power Plant Control Room Simulator

Li Xiyun, Wang Xi, Liang Chenchen, Wang Shaohua

ICONE 2018; V001T04A004https://doi.org/10.1115/ICONE26-81163

Abstract

View Articletitled, Application of Virtual Reality Technology in Nuclear Power Plant Control Room Simulator

PDF

Topics: Control rooms , Nuclear power stations , Virtual reality , Design , Machinery , Computer software , Optimization , Power stations

Simulated Training Instrument of Nuclear Radiation Reconnaissance Based on an Improved Ellipse Numerical Model

Shuijun He, Manchun Liang, Guofeng Su, J. T. He

ICONE 2018; V001T04A005https://doi.org/10.1115/ICONE26-81250

Abstract

View Articletitled, Simulated Training Instrument of Nuclear Radiation Reconnaissance Based on an Improved Ellipse Numerical Model

PDF

Topics: Computer simulation , Instrumentation , Nuclear radiation

Application of Monte Carlo Methods in Reactor Protection System Reliability Research

Duo Li, Zhaojun Hao, Shuqiao Zhou, Chao Guo

ICONE 2018; V001T04A006https://doi.org/10.1115/ICONE26-81300

Abstract

View Articletitled, Application of Monte Carlo Methods in Reactor Protection System Reliability Research

PDF

Topics: Monte Carlo methods , Reactor protection systems , Reliability , Event history analysis , Simulation , Nuclear power stations , Chain , Complex systems , Control systems , Instrumentation

A Research on System Error Correction for a High Temperature Hydrogen Detector Based on Neural Network Technique

Qi Zhenfeng, Zhang Yiwang, Li Wei, Yuan Yidan

ICONE 2018; V001T04A007https://doi.org/10.1115/ICONE26-81301

Abstract

View Articletitled, A Research on System Error Correction for a High Temperature Hydrogen Detector Based on Neural Network Technique

PDF

Topics: Artificial neural networks , Errors , High temperature , Hydrogen , Sensors , Thermal conductivity , Accidents , Algorithms , Nuclear power stations , Pressure

Internal Vibration Source Analysis of AMB-Rotor System in HTR-PM Primary Helium Circulator

Jinpeng Yu, Lei Zhao

ICONE 2018; V001T04A008https://doi.org/10.1115/ICONE26-81339

Abstract

View Articletitled, Internal Vibration Source Analysis of AMB-Rotor System in HTR-PM Primary Helium Circulator

PDF

Topics: Helium , Rotors , Vibration , Anisotropy , Errors , Accuracy and precision , Displacement measurement , Sensors , Displacement , Feedback

The Security Vulnerability Analysis of Nuclear Power Digital Instrument Control Platform NASPIC

Hua Liu, Xiao-Hua Yang, Zhao-hui Liu, Meng Li, Zhi Chen, Zhigang Feng, Qing Zhao

ICONE 2018; V001T04A009https://doi.org/10.1115/ICONE26-81486

Abstract

View Articletitled, The Security Vulnerability Analysis of Nuclear Power Digital Instrument Control Platform NASPIC

PDF

Topics: Instrumentation , Nuclear power , Security , Nuclear power stations , Computer software , Embedded systems , Industrial controls

A Novel More Reliable and Extensible Architecture of Instrumentation and Control Systems

Shuqiao Zhou, Chao Guo, Duo Li, Xiaojin Huang

ICONE 2018; V001T04A010https://doi.org/10.1115/ICONE26-81570

Abstract

View Articletitled, A Novel More Reliable and Extensible Architecture of Instrumentation and Control Systems

PDF

Topics: Control systems , Instrumentation , Reliability , Nuclear power stations , Safety , Security , Small modular reactors , Storage

Prediction and Sensibility Analysis for Nuclear Safety-Critical Software Reliability of DCS

Liu Ying, Wang Ya-feng, Pang Bo, Tang Lei, Feng Bo, Cao Guo-hai

ICONE 2018; V001T04A011https://doi.org/10.1115/ICONE26-81647

Abstract

View Articletitled, Prediction and Sensibility Analysis for Nuclear Safety-Critical Software Reliability of DCS

PDF

Topics: Computer software , Reliability , Safety , Failure , Event history analysis , Nuclear power stations

Research on Algorithm of Sump Level Operator Assisted Support Program for PWR Nuclear Power Plant

Liu Qiaofen, Xiao Sanping, Liu Yu, Liu Xichao, Jiang Xulun

ICONE 2018; V001T04A012https://doi.org/10.1115/ICONE26-81714

Abstract

View Articletitled, Research on Algorithm of Sump Level Operator Assisted Support Program for PWR Nuclear Power Plant

PDF

Topics: Algorithms , Nuclear power stations , Pressurized water reactors , Leakage flows , Computational methods , Leakage , Leak-before-break , Nuclear reactor coolants , Nuclear reactor safety

The Cloud Model Theory of Intelligent Control Method for Non-Minimum-Phase and Non-Self-Balancing System in Nuclear Power

Mo Tao, Ruotong Qu, Zhiwu Ke, Zhaoxu Chen, Xianling Li, Yi Feng

ICONE 2018; V001T04A013https://doi.org/10.1115/ICONE26-81829

Abstract

View Articletitled, The Cloud Model Theory of Intelligent Control Method for Non-Minimum-Phase and Non-Self-Balancing System in Nuclear Power

PDF

Topics: Nuclear power , Water , Uncertainty , Control systems , Ambiguity , Boilers , Chaos , Gaussian distribution , Stability , Artificial intelligence

FMEDA and FIT-Based Safety Assessment of NPP I&C Systems Considering Expert Uncertainty

Alexander Yasko, Eugene Babeshko, Vyacheslav Kharchenko

ICONE 2018; V001T04A014https://doi.org/10.1115/ICONE26-82048

Abstract

View Articletitled, FMEDA and FIT-Based Safety Assessment of NPP I&C Systems Considering Expert Uncertainty

PDF

Topics: Nuclear power stations , Safety , Uncertainty , Computer software , Reliability , Failure mechanisms , Testing , Aerospace industry , Errors , Failure data

Research on Nuclear Power Plant Safety Functional Requirements Analysis and Function Allocation

Jia Ming, Huang Huan, Zhang Xuegang

ICONE 2018; V001T04A015https://doi.org/10.1115/ICONE26-82230

Abstract

View Articletitled, Research on Nuclear Power Plant Safety Functional Requirements Analysis and Function Allocation

PDF

Topics: Nuclear power stations , Safety , Accidents , Machinery , Design , Control rooms , Pumps , Valves

NPP I&C Safety Assessment by Aggregation of Formal Techniques

Eugene Babeshko, Vyacheslav Kharchenko, Kostiantyn Leontiiev, Oleg Odarushchenko, Oleksiy Strjuk

ICONE 2018; V001T04A016https://doi.org/10.1115/ICONE26-82270

Abstract

View Articletitled, NPP I&C Safety Assessment by Aggregation of Formal Techniques

PDF

Topics: Nuclear power stations , Safety , Computer software , Failure mode and effects analysis , Computers , Control systems , Design , Failure mechanisms , Flow (Dynamics) , Hardware

Evaluation of Electromagnetic Fields From Wireless Technologies in a Nuclear Plant

Mauro Cappelli, Vanni Lopresto, Riccardo Cecchi, Gaetano Marrocco

ICONE 2018; V001T04A017https://doi.org/10.1115/ICONE26-82290

Abstract

View Articletitled, Evaluation of Electromagnetic Fields From Wireless Technologies in a Nuclear Plant

PDF

Topics: Electromagnetic fields , Nuclear power stations , Simulation , Modeling , Power stations

Multi-Diversity for FPGA Platform Based NPP I&C Systems: New Possibilities and Assessment Technique

Vyacheslav Kharchenko, Andriy Kovalenko, Kostiantyn Leontiiev, Artem Panarin, Vyacheslav Duzhy

ICONE 2018; V001T04A018https://doi.org/10.1115/ICONE26-82377

Abstract

View Articletitled, Multi-Diversity for FPGA Platform Based NPP I&C Systems: New Possibilities and Assessment Technique

PDF

Topics: Nuclear power stations , Algorithms , Maintenance , Redundancy (Engineering) , Risk , Buses , Control systems , Cycles , Failure , Hardware

Analysis of the Alarm Generation and Display for the Reactor Accidents in HTR-PM

Chao Guo, Shuqiao Zhou, Duo Li, Xiaojin Huang

ICONE 2018; V001T04A019https://doi.org/10.1115/ICONE26-82483

Abstract

View Articletitled, Analysis of the Alarm Generation and Display for the Reactor Accidents in HTR-PM

PDF

Topics: Accidents , Nuclear power stations , Design , Control rooms , Optimization , Reactor protection systems , Safety , Signals , Steam turbines , Very high temperature reactors

Design Optimization of Modernization of I&C System Using Digital Technology in NPPs

Longqiang Zhang, Jiahong Yan, Weining Zhao, Weijun Huang

ICONE 2018; V001T04A020https://doi.org/10.1115/ICONE26-82498

Abstract

View Articletitled, Design Optimization of Modernization of I&C System Using Digital Technology in NPPs

PDF

Topics: Design , Nuclear power stations , Optimization , Control systems , Construction , Assembly lines , Economics , Engineers , Instrumentation , Nuclear power

Dynamic Model of a Seawater Desalination Plant Based on the Nuclear Heating Reactor and MED-TVC

Yifei Pan, Zhe Dong

ICONE 2018; V001T04A021https://doi.org/10.1115/ICONE26-82556

Abstract

View Articletitled, Dynamic Model of a Seawater Desalination Plant Based on the Nuclear Heating Reactor and MED-TVC

PDF

Topics: Dynamic models , Heating , Seawater , Design , Heat , Compression , Control systems , Dynamic modeling , Energy resources , Modeling

Design and Feasibility Analysis of the Electricity Generation System Based on Residual Heat

Zhe Dong, Miao Liu, Yifei Pan

ICONE 2018; V001T04A022https://doi.org/10.1115/ICONE26-82558

Abstract

View Articletitled, Design and Feasibility Analysis of the Electricity Generation System Based on Residual Heat

PDF

Topics: Design , Electric power generation , Heat , Cooling , Generators , Instrumentation , Air flow , Density , Dynamics (Mechanics) , Electromagnetic induction

Verification of Alarm Displays for the Nuclear Power Plant With Two Modular High-Temperature Gas-Cooled Reactors

Jia Qianqian, Guo Chao, Li Jianghai, Qu Ronghong

ICONE 2018; V001T04A023https://doi.org/10.1115/ICONE26-82561

Abstract

View Articletitled, Verification of Alarm Displays for the Nuclear Power Plant With Two Modular High-Temperature Gas-Cooled Reactors

PDF

Topics: Nuclear power stations , Very high temperature reactors , Control rooms , Construction , Design , Human factors , Integrated systems , Machinery

Innovative Nuclear Power Plant Design and SMRs

A Combined Small Modular Reactor and Gas Turbine Cycle With Reheat

Robert Stakenborghs, Gregory Kramer

ICONE 2018; V001T13A001https://doi.org/10.1115/ICONE26-81002

Abstract

View Articletitled, A Combined Small Modular Reactor and Gas Turbine Cycle With Reheat

PDF

Topics: Cycles , Gas turbines , Small modular reactors , Power stations , Carbon dioxide , Combined cycle gas turbines , Emissions , Energy generation , Exhaust systems , Fuels

Extended Ultimate Response Measures for Offshore Nuclear Power Plant Under Barge-Reactor Coupled Conditions

Jue Wang, Longze Li, Chen Hu, Wang Cong

ICONE 2018; V001T13A002https://doi.org/10.1115/ICONE26-81159

Abstract

View Articletitled, Extended Ultimate Response Measures for Offshore Nuclear Power Plant Under Barge-Reactor Coupled Conditions

PDF

Topics: Nuclear power stations , Ocean engineering , Seawater , Boilers , Design , Dimensions , Hazards , Heat , Accidents , Computers

Approach to UK SMR Component Design

Christopher D. Bell

ICONE 2018; V001T13A003https://doi.org/10.1115/ICONE26-81188

Abstract

View Articletitled, Approach to UK SMR Component Design

PDF

Topics: Design , Inspection , Manufacturing , Safety , Carbon , Design for Manufacturing , Energy generation , Failure , Failure mechanisms , Nuclear power stations

Upgrade and Shakedown Test of a High Temperature Fluoride Salt Test Loop

Xiangbo Kong, Yuan Fu, Jianyu Zhang, Huiju Lu, Naxiu Wang

ICONE 2018; V001T13A004https://doi.org/10.1115/ICONE26-81222

Abstract

View Articletitled, Upgrade and Shakedown Test of a High Temperature Fluoride Salt Test Loop

PDF

Topics: High temperature , Storage tanks , Flow (Dynamics) , Heat exchangers , Pipes , Pumps , Temperature , Alloys , Centrifugal pumps , Convection

Preliminary LOCA Analysis of Heating-Reactor of Advanced Low-Pressurized and Passive Safety System (HAPPY)

Mian Xing, Zhaocan Meng, Xiaotao Liao, Canhui Sun, Shuming Zhang, Yaodong Chen, Xiao Hu, Peidong Sun, Huijing Jiang

ICONE 2018; V001T13A005https://doi.org/10.1115/ICONE26-81271

Abstract

View Articletitled, Preliminary LOCA Analysis of Heating-Reactor of Advanced Low-Pressurized and Passive Safety System (HAPPY)

PDF

Topics: Heating , Safety , Design , Conceptual design , Central heating , Cooling , Heat , Optimization , Reactor vessels , Seawater

Estimation of Mitigation Effects of Sodium Nanofluid for SGTR Accidents in SFR

Kenta Ichikawa, Hironori Kanda, Naoki Yoshioka, Kuniaki Ara, Jun-ichi Saito, Keiichi Nagai

ICONE 2018; V001T13A006https://doi.org/10.1115/ICONE26-81309

Abstract

View Articletitled, Estimation of Mitigation Effects of Sodium Nanofluid for SGTR Accidents in SFR

PDF

Topics: Accidents , Nanofluids , Sodium , Sodium fast reactors , Water , Coolants , Design , Temperature , Boilers , Damage

Integrated Design of a Reactor Core for the Rolls-Royce Small Modular Reactor Project

Simon de Haas, David Chu, Kevin Ellis, Matthew White, Ben Lindley, Peter Smith, Julian Murgatroyd, Andrew Grief, Mike Leddy, Mike Yule

ICONE 2018; V001T13A007https://doi.org/10.1115/ICONE26-81311

Abstract

View Articletitled, Integrated Design of a Reactor Core for the Rolls-Royce Small Modular Reactor Project

PDF

Topics: Design , Small modular reactors , Safety , Cycles , Corporate average fuel economy , Engineering disciplines , Fuel efficiency , Fuels , Physics , Power stations

Control Strategy Investigation for a Multi-Purpose Modular Small Pressurized Water Reactor With Once-Through Steam Generators

Qian Ma, Peiwei Sun

ICONE 2018; V001T13A008https://doi.org/10.1115/ICONE26-81318

Abstract

View Articletitled, Control Strategy Investigation for a Multi-Purpose Modular Small Pressurized Water Reactor With Once-Through Steam Generators

PDF

Topics: Boilers , Pressurized water reactors , Feedwater , Flow (Dynamics) , Steam , Stress , Turbines , Coolants , Pressure vessels , China

Geometry Survey on the Convex Shaped Core for Recriticality Prevention Against CDA in Sodium-Cooled Fast Reactor

Keiko Chitose, Yoshiaki Tachi, Toshio Wakabayashi, Naoyuki Takaki

ICONE 2018; V001T13A009https://doi.org/10.1115/ICONE26-81331

Abstract

View Articletitled, Geometry Survey on the Convex Shaped Core for Recriticality Prevention Against CDA in Sodium-Cooled Fast Reactor

PDF

Topics: Geometry , Sodium fast reactors , Fuels , Compacting , Neutrons , Coolants , Deformation , Design , Feedback , Leakage

A Methodology to Determine SMR Build Schedule and the Impact of Modularisation

Clara A. Lloyd, Anthony Roulstone

ICONE 2018; V001T13A010https://doi.org/10.1115/ICONE26-81550

Abstract

View Articletitled, A Methodology to Determine SMR Build Schedule and the Impact of Modularisation

PDF

Topics: Construction , Design , Manufacturing , Pressurized water reactors , Quality control , Small modular reactors , Water

Comparative Study of Helium Turbine Brayton Cycle and Supercritical CO₂ Brayton Cycle for HTGR

Gang Zhao, Xiaoyong Yang, Ping Ye, Jie Wang, Wei Peng

ICONE 2018; V001T13A011https://doi.org/10.1115/ICONE26-81561

Abstract

View Articletitled, Comparative Study of Helium Turbine Brayton Cycle and Supercritical CO2 Brayton Cycle for HTGR

PDF

Topics: Brayton cycle , Helium , Supercritical carbon dioxide , Turbines , Very high temperature reactors , Cycles , China , Steam , Compression , Construction

We Never Built Small Modular Reactors (SMRs), but What Do We Know About Modularization in Construction?

Benito Mignacca, Giorgio Locatelli, Mahmoud Alaassar, Diletta Colette Invernizzi

ICONE 2018; V001T13A012https://doi.org/10.1115/ICONE26-81604

Abstract

View Articletitled, We Never Built Small Modular Reactors (SMRs), but What Do We Know About Modularization in Construction?

PDF

Topics: Construction , Small modular reactors , Compression , Cost benefit analysis , Nuclear construction , Project management , Transportation systems

Design and Non-Proliferation Viability of Small Modular Reactors

Zafar ullah Koreshi

ICONE 2018; V001T13A013https://doi.org/10.1115/ICONE26-81651

Abstract

View Articletitled, Design and Non-Proliferation Viability of Small Modular Reactors

PDF

Topics: Design , Small modular reactors , Nuclear power , Carbon , Emissions , Nuclear reactors , Power density , Risk , Safety , Signals

Hydrogen Risk Reducing Technology in Small Modular Reactor

YanLin Chen, XueFeng Lv

ICONE 2018; V001T13A014https://doi.org/10.1115/ICONE26-81705

Abstract

View Articletitled, Hydrogen Risk Reducing Technology in Small Modular Reactor

PDF

Topics: Hydrogen , Risk , Small modular reactors , Containment , Accidents , Blasting , Control systems , Domes (Structural elements) , Flames , Oxygen

A Concept of Intermediate Heat Exchanger for High-Temperature Gas Reactor Hydrogen and Power Cogeneration System

Noriaki Hirota, Atsuhiko Terada, Xing L. Yan, Kohei Tanaka, Akihito Otani

ICONE 2018; V001T13A015https://doi.org/10.1115/ICONE26-81718

Abstract

View Articletitled, A Concept of Intermediate Heat Exchanger for High-Temperature Gas Reactor Hydrogen and Power Cogeneration System

PDF

Topics: Combined heat and power , Heat exchangers , High temperature , Hydrogen , Nuclear reactors , Conceptual design , Design , Gas turbines , Construction , Creep

Proposed License Structure of Small Modular Reactor in China

Zheng Hua, Wei Shuhong

ICONE 2018; V001T13A016https://doi.org/10.1115/ICONE26-81985

Abstract

View Articletitled, Proposed License Structure of Small Modular Reactor in China

PDF

Topics: China , Licensing , Small modular reactors , Design , Construction , Light water reactors , Nuclear power stations , Safety

A Core Design of Innovative Breeder BWR

Guo Rui, Akifumi Yamaji, Yun Cai, Xingjie Peng

ICONE 2018; V001T13A017https://doi.org/10.1115/ICONE26-82079

Abstract

View Articletitled, A Core Design of Innovative Breeder BWR

PDF

Topics: Boiling water reactors , Design , Manufacturing , Water , Atoms , Cooling , Fuels , Neutrons , Economics , Heavy metals

Numerical Study on the Two-Phase Flow for a Gas/Liquid Metal Magnetohydrodynamic Generator

Meng-Ran Liao, Chun-Hui Dai, Can Ma, Yong Liu, Zheng-Xing Zhao, Zhou-Yang Liu

ICONE 2018; V001T13A018https://doi.org/10.1115/ICONE26-82231

Abstract

View Articletitled, Numerical Study on the Two-Phase Flow for a Gas/Liquid Metal Magnetohydrodynamic Generator

PDF

Topics: Generators , Liquid metals , Magnetohydrodynamics , Two-phase flow , Fluids , Porosity , Temperature , Bubbles , Cycles , Dimensions

A Multi-Objective Optimization of the Reactor Power Plant

Chen Lei, Jia Zhen, Wang Cong, Gong Zili, Liao Yi, Hu Chen

ICONE 2018; V001T13A019https://doi.org/10.1115/ICONE26-82239

Abstract

View Articletitled, A Multi-Objective Optimization of the Reactor Power Plant

PDF

Topics: Pareto optimization , Power stations , Nuclear power stations , Boilers , Weight (Mass) , Algorithms , Condensers (steam plant) , Design , Optimization , Pipes

Dynamic Control Analysis of the AFR-100 SMR SFR With a Supercritical CO₂ Cycle and Dry Air Cooling: Part I — Plant Control Optimization

Anton Moisseytsev, James J. Sienicki

ICONE 2018; V001T13A020https://doi.org/10.1115/ICONE26-82292

Abstract

View Articletitled, Dynamic Control Analysis of the AFR-100 SMR SFR With a Supercritical CO2 Cycle and Dry Air Cooling: Part I — Plant Control Optimization

PDF

Topics: Cooling , Cycles , Optimization , Sodium fast reactors , Supercritical carbon dioxide , Brayton cycle , Nuclear reactors , Power converters , Small modular reactors , Stress

Dynamic Control Analysis of the AFR-100 SMR SFR With a Supercritical CO₂ Cycle and Dry Air Cooling: Part II — Plant Control Under Varying Ambient Conditions

Anton Moisseytsev, James J. Sienicki

ICONE 2018; V001T13A021https://doi.org/10.1115/ICONE26-82295

Abstract

View Articletitled, Dynamic Control Analysis of the AFR-100 SMR SFR With a Supercritical CO2 Cycle and Dry Air Cooling: Part II — Plant Control Under Varying Ambient Conditions

PDF

Topics: Cooling , Cycles , Sodium fast reactors , Supercritical carbon dioxide , Brayton cycle , Nuclear reactors , Power converters , Small modular reactors , Temperature

European Utility Requirements for Advanced LWR Issue of EUR Revision E and Ongoing Assessments

Peter Chappell, Guillaume Jacquart, Giovanni Ferraro, Olli Kymäläinen

ICONE 2018; V001T13A022https://doi.org/10.1115/ICONE26-82343

Abstract

View Articletitled, European Utility Requirements for Advanced LWR Issue of EUR Revision E and Ongoing Assessments

PDF

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

iB1350: Part 1 — A Generation III.7 Reactor iB1350 and Defense in Depth (DiD)

Takashi Sato, Keiji Matsumoto, Kenji Hosomi, Keisuke Taguchi

ICONE 2018; V001T13A023https://doi.org/10.1115/ICONE26-82428

Abstract

View Articletitled, iB1350: Part 1 — A Generation III.7 Reactor iB1350 and Defense in Depth (DiD)

PDF

Topics: Defense industry , Safety , Containment , Containment buildings , Boiling water reactors , Condensers (steam plant) , Containment systems , Cooling systems , Design , Domes (Structural elements)

Status of District Heating Reactor and its Development Prospects in China

Jing Zhao, Fei Xie, Zhihong Liu

ICONE 2018; V001T13A024https://doi.org/10.1115/ICONE26-82445

Abstract

View Articletitled, Status of District Heating Reactor and its Development Prospects in China

PDF

Topics: Central heating , China , Heating , Low temperature , Construction , Design , Heat , Nuclear power , Nuclear reactors , Power stations

iB1350: Part 2 — Level1 PRA Considering Optimization of Safety Systems for the iB1350

Tanaka Go, Sato Takashi, Komori Yuji, Matsumoto Keiji

ICONE 2018; V001T13A025https://doi.org/10.1115/ICONE26-82552

Abstract

View Articletitled, iB1350: Part 2 — Level1 PRA Considering Optimization of Safety Systems for the iB1350

PDF

Topics: Optimization , Safety , Accidents , Containment , Fukushima nuclear disaster, Japan, 2011 , Heat , Boiling water reactors , Condensers (steam plant) , Cooling systems , Cylinders