Volumes | International Conference on Nuclear Engineering | American Society of Mechanical Engineers Digital Collection

Topics: Metals , Nuclear power stations , Ultrasonic testing , Welded joints , ASME Boiler and Pressure Vessel Code , China , Engineering standards , In-service inspection , Inspection , Nondestructive evaluation

Interaction of a Nuclear Power Plant With the Egyptian Electrical Grid Based on PSS/E

S. Othman, H. M. Mahmoud, S. A. Kotb

ICONE 2010; 27-32https://doi.org/10.1115/ICONE18-29051

Abstract

View Articletitled, Interaction of a Nuclear Power Plant With the Egyptian Electrical Grid Based on PSS/E

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Topics: Nuclear power stations , Power grids , Power systems (Machinery)

The Operation Characteristics of the Fuel Handling System of HTR-10

Peng Huang, Xihua Liang, Xiaoming Chen

ICONE 2010; 33-39https://doi.org/10.1115/ICONE18-29095

Abstract

View Articletitled, The Operation Characteristics of the Fuel Handling System of HTR-10

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Topics: Fuels , Control systems , Coolants , Helium , Very high temperature reactors

Introduction of Interim Storage of SNF in INET

Peng Huang, Xiaoming Chen, Lixin Jia

ICONE 2010; 41-45https://doi.org/10.1115/ICONE18-29096

Abstract

View Articletitled, Introduction of Interim Storage of SNF in INET

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Topics: Storage , Ceramics , Gas cooled reactors , Heating , High temperature , Leakage , Safety , Spent nuclear fuels , Transportation systems

The Analysis of Effect on the Piping Due to the Displacement of EPR Nuclear Island Buildings

Junwei Wang, Zhouhong Zhang, Gaofeng Wu

ICONE 2010; 47-52https://doi.org/10.1115/ICONE18-29133

Abstract

View Articletitled, The Analysis of Effect on the Piping Due to the Displacement of EPR Nuclear Island Buildings

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Topics: Displacement , Pipes , Stress , Stress analysis (Engineering) , Structures

Commercial-Grade Item Dedication for Nuclear Safety-Related Application

Yao-Tung Hsu, Ming-Huei Chen

ICONE 2010; 53-58https://doi.org/10.1115/ICONE18-29136

Abstract

View Articletitled, Commercial-Grade Item Dedication for Nuclear Safety-Related Application

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Topics: Safety , Nuclear power stations , Equipment qualification , Engineering standards , Engines , Fittings , Motors , Nuclear energy research , Pipes

Design, Operation and Maintenance of Thermal Hydraulic Instrumentation System of HTR-10

Liqiang Wei, Shuoping Zhong

ICONE 2010; 59-65https://doi.org/10.1115/ICONE18-29139

Abstract

View Articletitled, Design, Operation and Maintenance of Thermal Hydraulic Instrumentation System of HTR-10

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Topics: Design , Instrumentation , Maintenance , Pressure , Temperature , Coolants , Flow (Dynamics) , Thermocouples , Very high temperature reactors , Construction

Condensate Polishing System for PWR Nuclear Power Plant

Ailing Wang

ICONE 2010; 67-72https://doi.org/10.1115/ICONE18-29147

Abstract

View Articletitled, Condensate Polishing System for PWR Nuclear Power Plant

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Topics: Condensed matter , Nuclear power stations , Polishing , Pressurized water reactors , Water , Flow (Dynamics) , Leakage , Electricity (Physics) , Nuclear reactors , Seawater

Investigations and Countermeasures for Deactivation of the Hydrogen Recombination Catalyst at Hamaoka Unit 4 and 5

Toru Kawasaki, Motohiro Aizawa, Hidehiro Iizuka, Koji Yamada, Mitsuo Kugimoto

ICONE 2010; 73-79https://doi.org/10.1115/ICONE18-29155

Abstract

View Articletitled, Investigations and Countermeasures for Deactivation of the Hydrogen Recombination Catalyst at Hamaoka Unit 4 and 5

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Topics: Catalysts , Countermeasures , Hydrogen , Sealants , Silicon , Pressure , Turbines , Condensation , Flax , Heat treating (Metalworking)

Development of Large Size Moisture Separator Reheater for Up to 1700 MW PWR Class

Issaku Fujita, Teruaki Sakata, Toshiki Kojima

ICONE 2010; 81-90https://doi.org/10.1115/ICONE18-29157

Abstract

View Articletitled, Development of Large Size Moisture Separator Reheater for Up to 1700 MW PWR Class

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Topics: Pressurized water reactors , Molten salt reactors , Flow (Dynamics) , Steam , Computational fluid dynamics , Pressure , Pressure drop , Turbines , Corrosion , Design

Centrifugal Pump Leak-Free Technology Introduction and Its Applications in EPR Nuclear Power Plant

Guohui Cong, Ling Zhang

ICONE 2010; 91-96https://doi.org/10.1115/ICONE18-29194

Abstract

View Articletitled, Centrifugal Pump Leak-Free Technology Introduction and Its Applications in EPR Nuclear Power Plant

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Topics: Centrifugal pumps , Leakage , Nuclear power stations , Pumps , Engines , Motors , Clearances (Engineering) , Fluids , High pressure (Physics) , Pressurized water reactors

Life Extension of the Fast Breeder Test Reactor

B. Anandapadmanaban, A. Babu, B. Babu, K. Dinesh, V. Ramanathan, G. Srinivasan

ICONE 2010; 97-102https://doi.org/10.1115/ICONE18-29277

Abstract

View Articletitled, Life Extension of the Fast Breeder Test Reactor

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Topics: Life extension , Fuels , Heat , Creep , Cycles , Design , Equipment qualification , Maintenance , Pumps , Safety

AP1000 Operation Procedures System and Development

Fang Wen

ICONE 2010; 103-108https://doi.org/10.1115/ICONE18-29316

Abstract

View Articletitled, AP1000 Operation Procedures System and Development

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Topics: American Petroleum Institute , China , Human factors , Nuclear power , Nuclear power stations , Workflow

Spread Spectrum Time Domain Reflectrometry Applied to Electrical Systems in Nuclear Power Plants

Gary M. Sandquist, Carl J. Sandquist

ICONE 2010; 109-111https://doi.org/10.1115/ICONE18-29324

Abstract

View Articletitled, Spread Spectrum Time Domain Reflectrometry Applied to Electrical Systems in Nuclear Power Plants

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Topics: Electronic systems , Nuclear power stations , Aircraft , Circuits , Integrated circuits , Nuclear reactors , Reflection , Safety , Signals , Transients (Dynamics)

Development of Ultrasonic Sensor for Under-Sodium Volumetric Inspection of Heat Exchanger Pipes

M. Takeishi, M. Yui, T. Kobayashi, F. Tsuri, S. Kotake

ICONE 2010; 113-119https://doi.org/10.1115/ICONE18-29370

Abstract

View Articletitled, Development of Ultrasonic Sensor for Under-Sodium Volumetric Inspection of Heat Exchanger Pipes

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Topics: Heat exchangers , Inspection , Pipes , Sodium , Ultrasonic transducers , Sensors , Diffusion bonding (Metals) , Electrical discharge machining , Low temperature , Stainless steel

The Investigation of Classification Management for SSCS Susceptible to Ageing in PWR

Fei Xue, Peng Liu, Xin-ming Meng, Wen-xin Ti, Lei Lin, Zhao-xi Wang, Guo-dong Zhang, Jia-wang Jiang

ICONE 2010; 121-124https://doi.org/10.1115/ICONE18-29378

Abstract

View Articletitled, The Investigation of Classification Management for SSCS Susceptible to Ageing in PWR

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Topics: Pressurized water reactors , China , Nuclear power stations , Evaluation methods , Licensing , Nuclear power , Nuclear power plant operations , Reliability , Safety

Progressive Evolution of the Core of the Fast Breeder Test Reactor

S. Varatharajan, K. V. Sureshkumar, K. V. Kasiviswanathan, G. Srinivasan

ICONE 2010; 125-130https://doi.org/10.1115/ICONE18-29404

Abstract

View Articletitled, Progressive Evolution of the Core of the Fast Breeder Test Reactor

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Topics: Breeder reactors , Electromagnetic induction , Engineering prototypes , Failure , Fast neutron reactors , Fuels , Heat , Irradiation (Radiation exposure) , Manufacturing , Nuclear fuel cycle

Study on Integrated Method for Constructing Proactive Trouble Prevention Knowledge Base

Hidekazu Yoshikawa, Ming Yang

ICONE 2010; 131-136https://doi.org/10.1115/ICONE18-29424

Abstract

View Articletitled, Study on Integrated Method for Constructing Proactive Trouble Prevention Knowledge Base

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Topics: Failure mechanisms , Failure mode and effects analysis , Flow (Dynamics)

The Energy-Saving Diagnosis of PWR Nuclear Power Station Based on the Thermo-Economic Analysis Model

Juan Chen, Tao Zhou, Ke Ran

ICONE 2010; 137-144https://doi.org/10.1115/ICONE18-29454

Abstract

View Articletitled, The Energy-Saving Diagnosis of PWR Nuclear Power Station Based on the Thermo-Economic Analysis Model

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Topics: Nuclear power stations , Pressurized water reactors , Thermoeconomics , Exergy , Flow (Dynamics) , Exergy analysis , Signals , Construction , Energy conservation , Fuels

Inspection of the Steam Generator Divider Plate

Filippo D’Annucci, Eric Lecour

ICONE 2010; 145-148https://doi.org/10.1115/ICONE18-29457

Abstract

View Articletitled, Inspection of the Steam Generator Divider Plate

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Topics: Boilers , Inspection , Manipulators , Radiation (Physics) , Welded joints

Estimation of SG TSP Blockage: Innovative Monitoring Through Dynamic Behavior Analysis

Mickael Midou, Julien Ninet, Alexandre Girard, Jean-Me´laine Favennec

ICONE 2010; 149-155https://doi.org/10.1115/ICONE18-29458

Abstract

View Articletitled, Estimation of SG TSP Blockage: Innovative Monitoring Through Dynamic Behavior Analysis

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Topics: Boilers , Circuits , Corrosion , Dynamics (Mechanics) , Exterior walls , Feedwater , Flow (Dynamics) , Fluids , Heat transfer , Maintenance

Evaluation of the Conservatism of NPP Safety Analysis Dose Calculations as Typical for Licensing Purposes

Nikolaus Arnold, Nikolaus Mu¨llner, Francesco D’Auria, Oscar Mazzantini

ICONE 2010; 157-162https://doi.org/10.1115/ICONE18-29465

Abstract

View Articletitled, Evaluation of the Conservatism of NPP Safety Analysis Dose Calculations as Typical for Licensing Purposes

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Topics: Licensing , Nuclear power stations , Safety , Accidents , Boundary-value problems , Computers , Decision making , Design , Gases , Plant personnel

Sealing Solutions for an Aging Reactor

Timothy M. Sykes

ICONE 2010; 163-169https://doi.org/10.1115/ICONE18-29470

Abstract

View Articletitled, Sealing Solutions for an Aging Reactor

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Topics: Design , Failure , Leakage , Nuclear reactors , Pressure , Pumps , Sealing (Process) , Testing , Water

Steam Generator Asset Management Program

Padmanabha J. Prabhu, Damian A. Testa

ICONE 2010; 171-176https://doi.org/10.1115/ICONE18-29471

Abstract

View Articletitled, Steam Generator Asset Management Program

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Topics: Boilers , Maintenance , Strategic planning , Inspection , Pressurized water reactors , Chemistry , Condition monitoring , Cost benefit analysis , Decision making , Life extension

Remote Field Eddy Current Testing for SG Inspection of Fast Reactor

Noriyasu Kobayashi, Souichi Ueno, Satoshi Nagai, Makoto Ochiai, Noboru Jimbo

ICONE 2010; 177-182https://doi.org/10.1115/ICONE18-29578

Abstract

View Articletitled, Remote Field Eddy Current Testing for SG Inspection of Fast Reactor

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Topics: Eddy current testing , Fast neutron reactors , Inspection , Magnetic fields , Sensors , Excitation systems , Wire mesh , Boilers , Flaw detection , Magnetic materials

State Oriented Procedure Application in Nuclear Power Plants in China

Qingming Yang

ICONE 2010; 183-186https://doi.org/10.1115/ICONE18-29591

Abstract

View Articletitled, State Oriented Procedure Application in Nuclear Power Plants in China

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Topics: China , Nuclear power stations , Accidents , Defense industry , Design , Nuclear power plant operations , Safety

Advances and Research Needs in Risk-Informed In-Service Inspection Methodology

X.-X. Yuan

ICONE 2010; 187-194https://doi.org/10.1115/ICONE18-29608

Abstract

View Articletitled, Advances and Research Needs in Risk-Informed In-Service Inspection Methodology

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Topics: Risk-informed in-service inspection , Inspection , Boiling water reactors , Nuclear industry , Nuclear power stations , Pressurized water reactors , Public utilities , Risk-based decision making , Safety

Evaluation on Radiological Consequence Induced by MSLB Accident With Alternative Source Term

Jingxi Li, Gaofeng Huang, Lili Tong

ICONE 2010; 195-200https://doi.org/10.1115/ICONE18-29615

Abstract

View Articletitled, Evaluation on Radiological Consequence Induced by MSLB Accident With Alternative Source Term

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Topics: Accidents

The Mass Concrete Construction Methodology Exploring and Practice for Ensuring Quality Applied in the First AP1000 Project

Xiao Liu

ICONE 2010; 201-206https://doi.org/10.1115/ICONE18-29656

Abstract

View Articletitled, The Mass Concrete Construction Methodology Exploring and Practice for Ensuring Quality Applied in the First AP1000 Project

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Topics: Concrete construction , Concretes , Construction , Nuclear power , Concrete cracking , Durability , Industrial research , Nuclear construction , Quality control , Safety

Maintenance Strategy for Branch Connection on the Hot Leg of Steam Generator in CANDU 6

Liang Zhao, Jianqun Hu, Zhigang Wu, Xin Wang

ICONE 2010; 207-212https://doi.org/10.1115/ICONE18-29700

Abstract

View Articletitled, Maintenance Strategy for Branch Connection on the Hot Leg of Steam Generator in CANDU 6

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Topics: Boilers , Maintenance

Improvement of Flange Tightening Method for Small Bore Low Rating Bolted Flanges

Masako Mori, Akira Nebu, Takashi Kanno

ICONE 2010; 213-221https://doi.org/10.1115/ICONE18-29701

Abstract

View Articletitled, Improvement of Flange Tightening Method for Small Bore Low Rating Bolted Flanges

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Topics: Bolted flanges , Flanges , Sealing (Process) , Gaskets , Dimensions , Lubricants , Workability , Pipes , Screws

Digital Image Evaluation Method for Digital Radiography

Masako Mori, Toshibumi Kashiwa, Yoshimitsu Aoki

ICONE 2010; 223-228https://doi.org/10.1115/ICONE18-29702

Abstract

View Articletitled, Digital Image Evaluation Method for Digital Radiography

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Topics: Evaluation methods , Inspection , Testing , Transfer functions

Performance Evaluation of Japanese Nuclear Power Plant Based on Open Data and Information (3)

Tadahisa Nagata, Ken-ichiro Sugiyama

ICONE 2010; 229-234https://doi.org/10.1115/ICONE18-29703

Abstract

View Articletitled, Performance Evaluation of Japanese Nuclear Power Plant Based on Open Data and Information (3)

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Topics: Nuclear power stations , Performance evaluation , Hazards , Maintenance , Failure mechanisms , Failure , Computational methods

BWR Recirculation Pump Adjustable Speed Drive Performance and Control Affects

James W. Morgan, Timothy Gode

ICONE 2010; 235-242https://doi.org/10.1115/ICONE18-29733

Abstract

View Articletitled, BWR Recirculation Pump Adjustable Speed Drive Performance and Control Affects

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Topics: Boiling water reactors , Pumps , Variable speed drives , Motors , Cables , Cooling , Cooling systems , Generators , Pressure , Stability

Management of Single Point Vulnerability Components

Yijun Yu, Ligen Xu, Xin Wang, Liansheng Wang

ICONE 2010; 243-250https://doi.org/10.1115/ICONE18-29738

Abstract

View Articletitled, Management of Single Point Vulnerability Components

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Topics: Chain , Nuclear power stations

LOCA Event Tree Analysis for Qinshan Phase III CANDU-6 PHWR NPP

Limin Zheng

ICONE 2010; 251-259https://doi.org/10.1115/ICONE18-29746

Abstract

View Articletitled, LOCA Event Tree Analysis for Qinshan Phase III CANDU-6 PHWR NPP

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Topics: Heavy water reactors , Nuclear power stations

Optimization of Production Plan and Risk Control in Qinshan III NPP

Jun Zhou

ICONE 2010; 261-265https://doi.org/10.1115/ICONE18-29802

Abstract

View Articletitled, Optimization of Production Plan and Risk Control in Qinshan III NPP

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Topics: Nuclear power stations , Optimization , Risk control , Maintenance , Performance evaluation , Risk analysis

Building Effective Organizations and Measures to Cope With Severe Weather in Qinshan III NPP

Jun Zhou

ICONE 2010; 267-271https://doi.org/10.1115/ICONE18-29803

Abstract

View Articletitled, Building Effective Organizations and Measures to Cope With Severe Weather in Qinshan III NPP

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Topics: Nuclear power stations , Storage

Modeling of NPP Canned Motor Pump Performance Degradation Assessment Based on Multi-Agent System

Liming Zhang

ICONE 2010; 273-277https://doi.org/10.1115/ICONE18-29812

Abstract

View Articletitled, Modeling of NPP Canned Motor Pump Performance Degradation Assessment Based on Multi-Agent System

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Topics: Engines , Modeling , Motors , Multi-agent systems , Nuclear power stations , Pumps , Concretes , Equipment performance

Dynamic Behavior of Cracked Cantilevered Pipes Conveying Fluid

Fengchun Cai, Fenggang Zang, Xianhui Ye

ICONE 2010; 279-287https://doi.org/10.1115/ICONE18-29826

Abstract

View Articletitled, Dynamic Behavior of Cracked Cantilevered Pipes Conveying Fluid

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Topics: Fluids , Fracture (Materials) , Pipes

Crack Growth Monitoring by Strain Measurement of the External Surface of Cracked Pipes: A Feasibility Study

Masayuki Kamaya, Koji Miyoshi

ICONE 2010; 289-294https://doi.org/10.1115/ICONE18-29843

Abstract

View Articletitled, Crack Growth Monitoring by Strain Measurement of the External Surface of Cracked Pipes: A Feasibility Study

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Topics: Fracture (Materials) , Pipes , Strain measurement , Pressure , Finite element analysis , Fitness-for-service , In-service inspection , Resolution (Optics) , Ultrasonic testing

The Outline of the Five-Percent Power Uprate Project in Tokai-2

Hitoshi Ohata, Toshikazu Nishibata, Tetsuya Onose

ICONE 2010; 295-299https://doi.org/10.1115/ICONE18-29845

Abstract

View Articletitled, The Outline of the Five-Percent Power Uprate Project in Tokai-2

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Topics: Power uprate , Electricity (Physics) , Nuclear power stations , Thermal energy , Boiling water reactors , Climate change , Countermeasures , Design , Governments , Licensing

Dr. Mainte: An Integrated Simulator for Optimization of Maintenance Strategies of Light Water Reactors

Yoshihiro Isobe, Mitsuyuki Sagisaka

ICONE 2010; 301-304https://doi.org/10.1115/ICONE18-29894

Abstract

View Articletitled, Dr. Mainte: An Integrated Simulator for Optimization of Maintenance Strategies of Light Water Reactors

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Topics: Light water reactors , Maintenance , Optimization , Decision making , Fracture mechanics , Nuclear power stations , Piping systems , Safety

Development of Remotely Operated Inspection Devices for BWR Internals

Mitsuaki Shimamura, Yutaka Togasawa, Hisashi Hozumi, Naruhiko Mukai, Yasuhiro Yuguchi

ICONE 2010; 305-309https://doi.org/10.1115/ICONE18-30033

Abstract

View Articletitled, Development of Remotely Operated Inspection Devices for BWR Internals

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Topics: Boiling water reactors , Inspection , Jet pumps , Remotely operated vehicles , Probes , Cables , Fuels , Machinery , Nozzles , Nuclear power stations

TRACE5 Simulation of Condensation-Induced Water Hammer Phenomena

S. Gallardo, V. Abella, G. Verdu´

ICONE 2010; 311-318https://doi.org/10.1115/ICONE18-30057

Abstract

View Articletitled, TRACE5 Simulation of Condensation-Induced Water Hammer Phenomena

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Topics: Condensation , Simulation , Water hammer , Flow (Dynamics) , Pipes , Pressure , Underground injection , Water , Boundary-value problems , Damage

Management and Practice of CPR1000 Nuclear Power Plants: Commissioning and Startup

Yu Yang, Wang Can

ICONE 2010; 319-323https://doi.org/10.1115/ICONE18-30150

Abstract

View Articletitled, Management and Practice of CPR1000 Nuclear Power Plants: Commissioning and Startup

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Topics: Nuclear power stations , Design , Inspection , Safety

Investigation on Integrity of JMTR Reactor Pressure Vessel

Hiroshi Ide, Akihiro Kimura, Hiroshi Miura, Yoshiharu Nagao, Naohiko Hori, Masanori Kaminaga

ICONE 2010; 325-334https://doi.org/10.1115/ICONE18-30238

Abstract

View Articletitled, Investigation on Integrity of JMTR Reactor Pressure Vessel

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Topics: Reactor vessels , Adhesion , Fatigue , Fluence (Radiation measurement) , Iron , Materials testing , Neutrons , Nozzles , Screws , Stress corrosion cracking

Snapshot Review of the Regulation of Gas Voids in Nuclear Steam Supply Systems in the United States

L. Ike Ezekoye, William M. Turkowski

ICONE 2010; 335-343https://doi.org/10.1115/ICONE18-30240

Abstract

View Articletitled, Snapshot Review of the Regulation of Gas Voids in Nuclear Steam Supply Systems in the United States

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Topics: Steam , Design , Emergency core cooling systems , Containment , Corrective actions , Heat , Licensing , Nuclear power stations , Pumps , Sprays

An Analytical Method for Modeling Two-Phase Gravity-Driven Drainage Systems in BOP Applications

Robert Stakenborghs, Michael L. Morgan, Jr.

ICONE 2010; 345-354https://doi.org/10.1115/ICONE18-30261

Abstract

View Articletitled, An Analytical Method for Modeling Two-Phase Gravity-Driven Drainage Systems in BOP Applications

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Topics: Drainage , Gravity (Force) , Modeling , Transients (Dynamics) , Design , Computer simulation , Feedwater , Flow (Dynamics) , Molten salt reactors , Nuclear power

The Development of SRCM and the Application at Home and Abroad

Lifei Yang, Jiang Hong

ICONE 2010; 355-360https://doi.org/10.1115/ICONE18-30281

Abstract

View Articletitled, The Development of SRCM and the Application at Home and Abroad

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Topics: Maintenance , Nuclear power stations

Execution of 18 Month Refueling Modification and Experience Feedback

Guo-long Sheng, Yang Pu

ICONE 2010; 361-365https://doi.org/10.1115/ICONE18-30291

Abstract

View Articletitled, Execution of 18 Month Refueling Modification and Experience Feedback

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Topics: Feedback , Nuclear fuel cycle , Nuclear power stations

A Procedure to Address the Fuel Rod Failures During LB-LOCA Transient in Atucha-2 NPP

Martina Adorni, Alessandro Del Nevo, Francesco D’Auria, Oscar Mazzantini

ICONE 2010; 367-376https://doi.org/10.1115/ICONE18-30329

Abstract

View Articletitled, A Procedure to Address the Fuel Rod Failures During LB-LOCA Transient in Atucha-2 NPP

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Topics: Failure , Fuel rods , Nuclear power stations , Transients (Dynamics) , Fuels , Computers , Neutrons , Physics , Thermomechanics , Acceptance criteria

The Advanced Installation Method of Containment Liner Plates

Woosung Kim, Jihong Park

ICONE 2010; 377-381https://doi.org/10.1115/ICONE18-30355

Abstract

View Articletitled, The Advanced Installation Method of Containment Liner Plates

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Topics: Containment , Plates (structures) , Concretes , Construction , Nuclear power stations

Fuel Cycle and Decommissioning

New Composite Materials for Decreasing of Radioactive Molecular Iodine in the Water Coolant on the Working and New Developed NPPS

S. A. Kulyukhin, L. V. Mizina, A. A. Tishina

ICONE 2010; 383-386https://doi.org/10.1115/ICONE18-29006

Abstract

View Articletitled, New Composite Materials for Decreasing of Radioactive Molecular Iodine in the Water Coolant on the Working and New Developed NPPS

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Topics: Composite materials , Coolants , Nuclear power stations , Water , Resins , Absorption , Sorption

Application of Formohydroxamic Acid in Nuclear Processing: Synthesis and Complexation With Technetium-99

Patricia Paviet-Hartmann, Amber Wright, Edward Mausolf, Keri Campbell, Frederic Poineau

ICONE 2010; 387-391https://doi.org/10.1115/ICONE18-29028

Abstract

View Articletitled, Application of Formohydroxamic Acid in Nuclear Processing: Synthesis and Complexation With Technetium-99

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Topics: Crystals , Diluents , Infrared spectroscopy , Nuclear fuel cycle , Nuclear magnetic resonance , Recycling , Resins , Ultraviolet-visible spectrophotometry , Uranium , Uranium mining

Researches on the In-Core Reload Design for TianWan Nuclear Power Station

Hongxia Wang

ICONE 2010; 393-397https://doi.org/10.1115/ICONE18-29057

Abstract

View Articletitled, Researches on the In-Core Reload Design for TianWan Nuclear Power Station

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Topics: Design , Nuclear power stations , Cycles , Leakage , China , Computation , Fuel rods , Gadolinium , Nuclear engineering , Nuclear fuel cycle

Simulation and Analysis: The Dose Distribution of KBS-3 Spent Nuclear Fuel Canister by MCNP

Bo Yang, He-xi Wu, Yi-bao Liu

ICONE 2010; 399-403https://doi.org/10.1115/ICONE18-29058

Abstract

View Articletitled, Simulation and Analysis: The Dose Distribution of KBS-3 Spent Nuclear Fuel Canister by MCNP

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Topics: Simulation , Spent nuclear fuels , Copper , Groundwater , Nodular iron , Nuclear industry , Nuclear power stations , Radioactive wastes , Corrosion , Health and safety

Acid Stimulation Used in In-Situ Leaching Uranium

Wen-sheng Liao, Li-min Wang, Yi-xuan Yao, Guo-ping Jiang, Hai-jun Zhao, Xin Huang

ICONE 2010; 405-411https://doi.org/10.1115/ICONE18-29066

Abstract

View Articletitled, Acid Stimulation Used in In-Situ Leaching Uranium

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Topics: In situ processing (Mining) , Uranium , Permeability , Damage , Flow (Dynamics) , Fluids , Minerals , Precipitation , Risk , Wells

The Implementation of Radiological Characterization for Reactor Decommissioning

Junxian Deng, Huasong Zhao, Xin Li, Feng Deng

ICONE 2010; 413-417https://doi.org/10.1115/ICONE18-29075

Abstract

View Articletitled, The Implementation of Radiological Characterization for Reactor Decommissioning

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Topics: Nuclear decommissioning , Radiological characterization , Density , Nuclear power , Radioactivity , Radioisotopes , Statistics

Selective Separation and Recovery of Cesium by Ammonium Tungstophosphate-Alginate Microcapsules

Hitoshi Mimura, Yan Wu, Yufei Wang, Yuichi Niibori, Isao Yamagishi, Masaki Ozawa, Takashi Ohnishi, Shinichi Koyama

ICONE 2010; 419-427https://doi.org/10.1115/ICONE18-29091

Abstract

View Articletitled, Selective Separation and Recovery of Cesium by Ammonium Tungstophosphate-Alginate Microcapsules

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Topics: Separation (Technology) , Crystals , Flow (Dynamics) , Biopolymers , Ion exchange , Metals , Zirconium

Testing of TRANSURANUS Code for RIA Analysis: The FK-1 NSRR Case

R. Calabrese, F. Vettraino

ICONE 2010; 429-436https://doi.org/10.1115/ICONE18-29098

Abstract

View Articletitled, Testing of TRANSURANUS Code for RIA Analysis: The FK-1 NSRR Case

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Topics: Accidents , Boiling water reactors , Cladding systems (Building) , Control systems , Coolants , Damage , Design , Electricity (Physics) , Enthalpy , Failure

Burn-Up Calibration and Error Analysis of HTR-10 Spherical Fuel Elements by Gamma Spectroscopy

Bing Xia, Fu Li, Zongxin Wu

ICONE 2010; 437-444https://doi.org/10.1115/ICONE18-29300

Abstract

View Articletitled, Burn-Up Calibration and Error Analysis of HTR-10 Spherical Fuel Elements by Gamma Spectroscopy

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Topics: Calibration , Error analysis , Fuels , Gamma ray spectrometry , Errors , Measurement systems , Graphite , Very high temperature reactors , Absorption , Alpha decay

N,N,N^′,N^′-Tetra-Methyl-3-Oxy-Pentane-1,5-Diamide (TMPDA): A Promising Back Extractant for Ln(III) and Zr(IV)

Meng Wei, Qian’ge He, Xuegang Liu, Jing Chen

ICONE 2010; 445-450https://doi.org/10.1115/ICONE18-29358

Abstract

View Articletitled, N,N,N′,N′-Tetra-Methyl-3-Oxy-Pentane-1,5-Diamide (TMPDA): A Promising Back Extractant for Ln(III) and Zr(IV)

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Topics: Zirconium , Crystal structure , Equilibrium (Physics) , Melting point , Temperature , Water

FCC-NG: The AREVA Safe Fresh Fuel Shipping Cask to Deliver the Future EPR™ Reactors

M. Doucet, P. Faye, Ch. Faignet, R. Babut, M. Landrieu, F. Marvaud, G. Romanet

ICONE 2010; 451-455https://doi.org/10.1115/ICONE18-29436

Abstract

View Articletitled, FCC-NG: The AREVA Safe Fresh Fuel Shipping Cask to Deliver the Future EPR™ Reactors

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Topics: Fuels

Nuclear Fuel Cycle: Which Strategy to Sustain Nuclear Renaissance?

Renaud Liberge, Marc Arslan

ICONE 2010; 457-463https://doi.org/10.1115/ICONE18-29574

Abstract

View Articletitled, Nuclear Fuel Cycle: Which Strategy to Sustain Nuclear Renaissance?

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Topics: Nuclear fuel cycle , Fuels , Recycling , Uranium , Nuclear power , Nuclear environmental management , Nuclear fuels , Sustainable development , Waste management

The Development and Innovation of Spent Fuel Reprocessing in Fuel Cycle

Guang Jun Chen, Yu Lin Cui, Guo Guo Zhang, Hong Jun Yao

ICONE 2010; 465-468https://doi.org/10.1115/ICONE18-29632

Abstract

View Articletitled, The Development and Innovation of Spent Fuel Reprocessing in Fuel Cycle

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Topics: Innovation , Nuclear fuel cycle , Spent nuclear fuels , Nuclear fission , Separation (Technology) , Uranium , Nuclear power stations , China , Combustion , Cycles

Synthesis of Results Obtained With Laser Cutting, a Promising Dismantling Tool

Guy Pilot

ICONE 2010; 469-475https://doi.org/10.1115/ICONE18-29751

Abstract

View Articletitled, Synthesis of Results Obtained With Laser Cutting, a Promising Dismantling Tool

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Topics: Aerosols , Cutting , Cutting tools , Gases , Generators , Laser cutting , Lasers , Nd-YAG lasers , Optical fiber , Plates (structures)

Transport of MOX Fuel: A Continuous Challenge

Je´roˆme Galtier

ICONE 2010; 477-482https://doi.org/10.1115/ICONE18-29875

Abstract

View Articletitled, Transport of MOX Fuel: A Continuous Challenge

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Topics: Fuels , Transportation systems , Nuclear power stations , Radioactive substances , Spent nuclear fuels , Boiling water reactors , Cooling , Nuclear fuel cycle , Nuclear industry , Pressurized water reactors

Poolside Examination Techniques Applied for Development of an Advanced PWR Fuel, PLUS7™

Jung-Cheol Shin, Jae-Ik Kim, Jung-Tack Kwon

ICONE 2010; 483-488https://doi.org/10.1115/ICONE18-29889

Abstract

View Articletitled, Poolside Examination Techniques Applied for Development of an Advanced PWR Fuel, PLUS7™

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Topics: Fuels , Pressurized water reactors , Fuel rods , Manufacturing , Design , Cycles , Irradiation (Radiation exposure) , Optical quality control , Rods

Extraction of Actinides and Lanthanides by Supercritical Fluid

Liyang Zhu, Wuhua Duan, Jingming Xu, Yongjun Zhu

ICONE 2010; 489-499https://doi.org/10.1115/ICONE18-29914

Abstract

View Articletitled, Extraction of Actinides and Lanthanides by Supercritical Fluid

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Topics: Supercritical fluids , Radioactive wastes , Supercritical fluid extraction , Nuclear fuels , Chemical engineering , Nuclear environmental management , Nuclear power , Radioactivity , Sustainable development

Treatment and Disposal of the Radioactive Graphite Waste

Lifang Tian, Mingfen Wen, Jing Chen

ICONE 2010; 501-509https://doi.org/10.1115/ICONE18-29985

Abstract

View Articletitled, Treatment and Disposal of the Radioactive Graphite Waste

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Topics: Graphite , Carbon , Contamination , Radioactive wastes , Carbon dioxide , Chemical processes , Decontamination , Gases , Nuclear fuels , Nuclear reactors

Development of Integrated Treatment System to Minimize LLLW From Purex Reprocessing Plant

Yasuhiro Suzuki, Yasutomi Morimoto, Hikari Egami, Takashi Kato, Mamoru Numata, Mitsuaki Kumazawa, Shekar Balagopal

ICONE 2010; 511-515https://doi.org/10.1115/ICONE18-30008

Abstract

View Articletitled, Development of Integrated Treatment System to Minimize LLLW From Purex Reprocessing Plant

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Topics: Radioactive waste processing , Radioactive wastes , Separation (Technology) , Spent nuclear fuels

Discussion of the Effects of AP1000 First Core Loading Pattern Design on Nuclear Power Plant Operation

Xuesong Li

ICONE 2010; 517-521https://doi.org/10.1115/ICONE18-30041

Abstract

View Articletitled, Discussion of the Effects of AP1000 First Core Loading Pattern Design on Nuclear Power Plant Operation

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Topics: Design , Nuclear power plant operations , Leakage , Safety , Cycles , Stress , Economic analysis , Equilibrium (Physics) , Fuel management , Fuels

Radioactive Waste Water Treatment by Inorganic Membrane System

Junfeng Li, Fujuan Han, Jianlong Wang

ICONE 2010; 523-527https://doi.org/10.1115/ICONE18-30092

Abstract

View Articletitled, Radioactive Waste Water Treatment by Inorganic Membrane System

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Topics: Membranes , Radioactive wastes , Water treatment

Based on 200L Barrels of Low-Level Solid Waste Encapsulates Device Design

Aiguo Shang, Jin Qin, Changjie Lu

ICONE 2010; 529-532https://doi.org/10.1115/ICONE18-30110

Abstract

View Articletitled, Based on 200L Barrels of Low-Level Solid Waste Encapsulates Device Design

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Topics: Design , Solid wastes , Paper products , Plastic products , Rubber

Scenarios for the Transmutation of Actinides in CANDU Reactors

Bronwyn Hyland, Brian Gihm

ICONE 2010; 533-543https://doi.org/10.1115/ICONE18-30123

Abstract

View Articletitled, Scenarios for the Transmutation of Actinides in CANDU Reactors

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Topics: Design , Fuels , Heat , Heavy water reactors , Isotopes , Manufacturing , Neutron flux , Nuclear environmental management , Nuclear fuels , Separation (Technology)

The Study on Pyrolytic Carbon Powder in the Coating Process of Fuel Particle for High-Temperature Gas-Cooled Reactor

Malin Liu, Bing Liu, Youlin Shao

ICONE 2010; 545-549https://doi.org/10.1115/ICONE18-30137

Abstract

View Articletitled, The Study on Pyrolytic Carbon Powder in the Coating Process of Fuel Particle for High-Temperature Gas-Cooled Reactor

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Topics: Carbon , Coating processes , Fuels , Particulate matter , Very high temperature reactors , Carbon black pigments , Drops , Electron microscopy , Lasers , Nanoparticles

Development of Superfine Spherical Silica Grout as an Alternative Grouting Material for the Geological Disposal of Long-Lived Radioactive Waste

Morimasa Naito, Hirokazu Kishi, Naomi Fukuoka, Tsutomu Yamada, Hideaki Ishida

ICONE 2010; 551-557https://doi.org/10.1115/ICONE18-30141

Abstract

View Articletitled, Development of Superfine Spherical Silica Grout as an Alternative Grouting Material for the Geological Disposal of Long-Lived Radioactive Waste

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Topics: Grouting , Radioactive wastes , Calcium hydroxide , Cements (Building materials) , Binders (Materials) , Particle size , Superplasticizers , Water , Workability

Efficiency of Sulfoaluminate Cement for Solidification of Simulated Radioactive Borate Liquid Waste

Qina Sun, Junfeng Li, Jianlong Wang, Shixi Ouyang, Qiang Li, Minghui Wu

ICONE 2010; 559-564https://doi.org/10.1115/ICONE18-30154

Abstract

View Articletitled, Efficiency of Sulfoaluminate Cement for Solidification of Simulated Radioactive Borate Liquid Waste

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Topics: Cements (Adhesives) , Solidification , Compressive strength , Water , Engineering standards , Freezing , Irradiation (Radiation exposure) , Fibers , Isotopes , Nuclides

The Application of Uniform Design Table in Cement Solidification of Nuclear Waste Resin

Minghui Wu, Qiang Li, Shixi Ouyang

ICONE 2010; 565-570https://doi.org/10.1115/ICONE18-30164

Abstract

View Articletitled, The Application of Uniform Design Table in Cement Solidification of Nuclear Waste Resin

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Topics: Cements (Adhesives) , Design , Radioactive wastes , Resins , Solidification , Raw materials

Study on Applicability of Simple Conversion Factor for In-Situ Activity Measurement

Yuko Onishi, Satoru Kawasaki, Masami Kato

ICONE 2010; 571-575https://doi.org/10.1115/ICONE18-30166

Abstract

View Articletitled, Study on Applicability of Simple Conversion Factor for In-Situ Activity Measurement

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Topics: Calibration , Certainty , Clearances (Engineering) , Computer software , Concretes , Density , Metals , Nuclear power stations , Radiation sources , Radioisotopes

Recent GEH Criticality Safety Activities in Support of the Nuclear Fuel Cycle

Lon Paulson, John Zino, Qi Ao

ICONE 2010; 577-580https://doi.org/10.1115/ICONE18-30227

Abstract

View Articletitled, Recent GEH Criticality Safety Activities in Support of the Nuclear Fuel Cycle

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Topics: Nuclear fuel cycle , Safety , Licensing , Packaging , Boiling water reactors , Computational methods , Design , Fuels , Manufacturing , Nuclear power

Plutonium Rock-Like Oxide Fuel (ROXf) System: Their Once-Through Burning and Usage

Ashraf Elsayed Mohamed Mohamed

ICONE 2010; 581-583https://doi.org/10.1115/ICONE18-30336

Abstract

View Articletitled, Plutonium Rock-Like Oxide Fuel (ROXf) System: Their Once-Through Burning and Usage

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Topics: Combustion , Fuels , Rocks , Light water reactors , Zirconium , Cooling , Irradiation (Radiation exposure) , Neutrons , Pressurized water reactors , Safety

Instrumentation and Controls (I&C)

Core Protection Calculator System: Past, Present, and Future

Peter L. Hung

ICONE 2010; 585-592https://doi.org/10.1115/ICONE18-29001

Abstract

View Articletitled, Core Protection Calculator System: Past, Present, and Future

PDF

Topics: Combustion engineering , Computer software , Computer technology , Computers , Construction , Design , Fuels , Licensing , Nuclear power stations , Nucleate boiling

Study on Technical Improvements for Human System Interface in the Main Control Room of LingAo 3 and 4

Shi Ji, Xiaomei Xu, Jianbo Zhang, Zhifang Wang

ICONE 2010; 593-598https://doi.org/10.1115/ICONE18-29011

Abstract

View Articletitled, Study on Technical Improvements for Human System Interface in the Main Control Room of LingAo 3 and 4

PDF

Topics: China , Construction , Control rooms , Control systems , Errors , Human factors , Nuclear power stations , Safety

The Application of FPGA for Anticipated Transients Without Scram Mitigation System

Mao-Sheng Tseng, Hui-Wen Huang, Ming-Huei Chen, Tsung-Chieh Cheng, Hsiang-Han Chung, Tzeng-Hsi Liu, Wen-Lung Yang, Ming-Chung Lee, Mao-Yuan Chen

ICONE 2010; 599-609https://doi.org/10.1115/ICONE18-29029

Abstract

View Articletitled, The Application of FPGA for Anticipated Transients Without Scram Mitigation System

PDF

Topics: Failure , Scram , Transients (Dynamics) , Nuclear power stations , Computer software , Computers , Boiling water reactors , Control systems , Defense industry , Errors

A Nodal Dynamic Model for Control System Simulation of the HTR-PM Reactor Core

Zhe Dong, Xiaojin Huang, Liangju Zhang

ICONE 2010; 611-618https://doi.org/10.1115/ICONE18-29055

Abstract

View Articletitled, A Nodal Dynamic Model for Control System Simulation of the HTR-PM Reactor Core

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Topics: Control systems , Dynamic models , Simulation , Design , High temperature , China , Computer simulation , Neutrons , Nuclear power stations , Nuclear reactors

Output-Feedback Load-Following Control of Nuclear Reactors Based on a Dissipative High Gain Filter

Zhe Dong, Xiaojin Huang, Liangju Zhang

ICONE 2010; 619-626https://doi.org/10.1115/ICONE18-29056

Abstract

View Articletitled, Output-Feedback Load-Following Control of Nuclear Reactors Based on a Dissipative High Gain Filter

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Topics: Feedback , Filters , Nuclear reactors , Stress , Control equipment , State feedback , Climate , Combustion , Computer simulation , Computer technology

Study of Unique Foam Detecting Sensor

Shengqiang Li, Shengyao Jiang, Shuoping Zhong, Wenran Wang, Hanliang Bo

ICONE 2010; 627-633https://doi.org/10.1115/ICONE18-29089

Abstract

View Articletitled, Study of Unique Foam Detecting Sensor

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Topics: Sensors , Accidents , Bubbly flow , Chemical engineering , Coolants , Cutting , Optics , Pressure , Pressurized water reactors , Steam

Developing Software Configuration Management System for Digital Instrumentation and Control (DI&C) System of Nuclear Power Plant

I-Hsin Chou, Hsueh-Wei Hsiao, Che-An Chang

ICONE 2010; 635-640https://doi.org/10.1115/ICONE18-29102

Abstract

View Articletitled, Developing Software Configuration Management System for Digital Instrumentation and Control (DI&C) System of Nuclear Power Plant

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Topics: Computer software , Instrumentation , Nuclear power stations , Regulations , Accounting , Databases , Design , Engineering prototypes , Software design

Simulation and Realization of Nuclear Instrument System

Guangxia Zuo, Bin He, Wenyan Ma, Xiaolin Qiu, Weihua Hui

ICONE 2010; 641-643https://doi.org/10.1115/ICONE18-29224

Abstract

View Articletitled, Simulation and Realization of Nuclear Instrument System

PDF

Topics: Instrumentation , Simulation

An Open-Walled Ionization Chamber Appropriate to Tritium Monitoring for Glovebox

Zhilin Chen, Heyi Wang

ICONE 2010; 645-649https://doi.org/10.1115/ICONE18-29230

Abstract

View Articletitled, An Open-Walled Ionization Chamber Appropriate to Tritium Monitoring for Glovebox

PDF

Topics: Ionization chambers , Pressure , Ionization , Mean free path , Pipelines , Pumps

Study and Design of Monitoring System of Reactor Coolant Pump in Nuclear Power Plant

Lei You, Fuchun Sun, Pan He, Hongkun Xu, Fang Fang

ICONE 2010; 651-657https://doi.org/10.1115/ICONE18-29232

Abstract

View Articletitled, Study and Design of Monitoring System of Reactor Coolant Pump in Nuclear Power Plant

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Topics: Design , Monitoring systems , Nuclear power stations , Nuclear reactor coolants , Pumps , Accidents , Algorithms , Failure , Fourier transforms , Performance

Effective Software Verification and Validation Approach for Nuclear Power Plant Digital Instrumentation and Control Systems

Steve Yang, Jun Ding, Huifang Miao, Jianxiang Zheng

ICONE 2010; 659-665https://doi.org/10.1115/ICONE18-29264

Abstract

View Articletitled, Effective Software Verification and Validation Approach for Nuclear Power Plant Digital Instrumentation and Control Systems

PDF

Topics: Control systems , Instrumentation , Nuclear power stations , Software verification , Cycles , Failure , Safety , China , Computer software , Construction

Test Facility Design for Integrated Digital Nuclear Reactor Protection System

Huasheng Xiong, Duo Li, Liangju Zhang

ICONE 2010; 667-671https://doi.org/10.1115/ICONE18-29286

Abstract

View Articletitled, Test Facility Design for Integrated Digital Nuclear Reactor Protection System

PDF

Topics: Design , Nuclear reactors , Test facilities , Reactor protection systems , Testing , Safety , Computer software , Nuclear power stations , Signals , Reliability

Design of an Ethernet Bus Interface Controller in a Nuclear Power Plant Simulator

Lixuan Lu, Dong Le

ICONE 2010; 673-677https://doi.org/10.1115/ICONE18-29305

Abstract

View Articletitled, Design of an Ethernet Bus Interface Controller in a Nuclear Power Plant Simulator

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Topics: Control equipment , Control systems , Design , Nuclear power stations

An Investigation on the Minimum Inventory of Human System Interfaces for Plant’s Safe Operation

Chih-Wei Yang, Tzu-Chung Yenn, Tsung-Chieh Cheng, Ming-Huei Chen, Tung-Ming Wu

ICONE 2010; 679-684https://doi.org/10.1115/ICONE18-29310

Abstract

View Articletitled, An Investigation on the Minimum Inventory of Human System Interfaces for Plant’s Safe Operation

PDF

Topics: Control rooms , Design , Emergencies , Failure , Instrumentation , Probabilistic risk assessment , Risk , Safety

The Development of a Generic Qualified Digital Platform

Victor S. S. Shyu, Ming-Huei Chen

ICONE 2010; 685-690https://doi.org/10.1115/ICONE18-29396

Abstract

View Articletitled, The Development of a Generic Qualified Digital Platform

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Topics: Collaboration , Computer software , Design , Failure , Instrumentation , Licensing , Manufacturing , Nuclear industry , Nuclear power stations , Safety

Full Digital I&C System in Tianwan Nuclear Power Station: Summary of Operational Experience and Analysis of Typical Events

Qingwei Shi, Ping Zhou

ICONE 2010; 691-699https://doi.org/10.1115/ICONE18-29487

Abstract

View Articletitled, Full Digital I&C System in Tianwan Nuclear Power Station: Summary of Operational Experience and Analysis of Typical Events

PDF

Topics: Nuclear power stations , Optimization , China , Computers , Control systems , Design , Instrumentation , Regulations , Safety , User interfaces

Design of Remote Control System for Far-Infrared Laser Interferometer

Nan Shi, Xiang Gao, Yinxian Jie, Erhui Wang, Yao Yang

ICONE 2010; 701-706https://doi.org/10.1115/ICONE18-29500

Abstract

View Articletitled, Design of Remote Control System for Far-Infrared Laser Interferometer

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Topics: Control systems , Design , Far infrared lasers , Interferometers , Lasers , Feedback , Control equipment , Gas flow , Machinery , Tokamaks

A Study on Fault Diagnosis Technology of Nuclear Power Plant Based on Decision Tree

Yu Mu, Hong Xia

ICONE 2010; 707-710https://doi.org/10.1115/ICONE18-29510

Abstract

View Articletitled, A Study on Fault Diagnosis Technology of Nuclear Power Plant Based on Decision Tree

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Topics: Fault diagnosis , Nuclear power stations

The Design and Simulation of Voltage-Preamplifier With Numerical-Controlled Plus

Wenyan Ma, Guojian Yu, Jian Chang

ICONE 2010; 711-713https://doi.org/10.1115/ICONE18-29512

Abstract

View Articletitled, The Design and Simulation of Voltage-Preamplifier With Numerical-Controlled Plus

PDF

Topics: Design , Simulation

Human Factors Engineering Verification and Validation: A Case Study of a Nuclear Power Plant

Fei Song, Shuhui Zhang

ICONE 2010; 715-721https://doi.org/10.1115/ICONE18-29556

Abstract

View Articletitled, Human Factors Engineering Verification and Validation: A Case Study of a Nuclear Power Plant

PDF

Topics: Control rooms , Ergonomics , Nuclear power stations , Design , Safety , Complex systems , Databases , Engineering disciplines , Human factors , Integrated systems

Study on a Methodology of Human Factor Engineering Operating Experience Review for Nuclear Power Plant

Danying Gu, Shuhui Zhang, Zhonghe Ning

ICONE 2010; 723-730https://doi.org/10.1115/ICONE18-29587

Abstract

View Articletitled, Study on a Methodology of Human Factor Engineering Operating Experience Review for Nuclear Power Plant

PDF

Topics: Human factors , Nuclear power stations

Design of Wireless Heterogeneous Framework for Radiation Monitoring in Nuclear Power Plant

Shouwei Gao, Danying Gu, Weidong Zhang, Xiaojin Zhu

ICONE 2010; 731-736https://doi.org/10.1115/ICONE18-29589

Abstract

View Articletitled, Design of Wireless Heterogeneous Framework for Radiation Monitoring in Nuclear Power Plant

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Topics: Design , Nuclear power stations , Radiation measurement , Wireless sensor networks

A Study on Human Reliability About Human Machine Interface in Accident Situation of Nuclear Power Plant

Pengfei Gu, Zhifang Wang, Jianbo Zhang

ICONE 2010; 737-742https://doi.org/10.1115/ICONE18-29596

Abstract

View Articletitled, A Study on Human Reliability About Human Machine Interface in Accident Situation of Nuclear Power Plant

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Topics: Accidents , Human reliability analysis , Machinery , Nuclear power stations , Reliability , Control rooms , Design , Safety , Boilers , Coolants

A Study About Human Workload Forecasting Method of Nuclear Power Plant

Guojin Jiang, Pengfei Gu, Yongbin Sun

ICONE 2010; 743-748https://doi.org/10.1115/ICONE18-29600

Abstract

View Articletitled, A Study About Human Workload Forecasting Method of Nuclear Power Plant

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Topics: Machinery , Nuclear power stations , Teams , Performance evaluation , Safety , Design , Human factors , Reliability

A Study on Evaluation Method About Human-Machine System Interface for Nuclear Power Plant

Yongbin Sun, Pengfei Gu, Guojin Jiang

ICONE 2010; 749-754https://doi.org/10.1115/ICONE18-29603

Abstract

View Articletitled, A Study on Evaluation Method About Human-Machine System Interface for Nuclear Power Plant

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Topics: Evaluation methods , Human-machine systems , Nuclear power stations , Computers , Control panels , Control rooms , Control systems , Design , Errors , Human factors

Diversity-Oriented FPGA-Based NPP I&C Systems: Safety Assessment, Development, Implementation

Vyacheslav S. Kharchenko, Eugenii S. Bakhmach, Alexandr A. Siora, Vladimir V. Sklyar, Viktor I. Tokarev

ICONE 2010; 755-764https://doi.org/10.1115/ICONE18-29754

Abstract

View Articletitled, Diversity-Oriented FPGA-Based NPP I&C Systems: Safety Assessment, Development, Implementation

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Topics: Nuclear power stations , Safety , Computer software , Cycles , Design , Engineering standards , Hardware , Redundancy (Engineering) , Transfer functions

Fault Detection and Identification in NPP Instruments Using Kernel Principal Component Analysis

Jianping Ma, Jin Jiang

ICONE 2010; 765-771https://doi.org/10.1115/ICONE18-29777

Abstract

View Articletitled, Fault Detection and Identification in NPP Instruments Using Kernel Principal Component Analysis

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Topics: Flaw detection , Instrumentation , Nuclear power stations , Principal component analysis , Errors , Sensors

CANDU Reactor Space-Time Kinetic Modeling for Load Following Control

Lingzhi Xia, Jin Jiang

ICONE 2010; 773-782https://doi.org/10.1115/ICONE18-29779

Abstract

View Articletitled, CANDU Reactor Space-Time Kinetic Modeling for Load Following Control

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Topics: Modeling , Spacetime , Stress , Neutron flux , Control systems , Design , Diffusion (Physics) , Eigenfunctions , Matlab , Neutrons

New Human-Machine Interface at VR-1 Training Reactor

Martin Kropi´k, Jan Rataj, Monika Jurˇicˇkova´

ICONE 2010; 783-792https://doi.org/10.1115/ICONE18-29799

Abstract

View Articletitled, New Human-Machine Interface at VR-1 Training Reactor

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Topics: Machinery

Adaptive Unbalance Vibration Control of Active Magnetic Bearing Systems for the HTR-10GT

Chao Hui, Lei Shi, Jie Wang, Suyuan Yu

ICONE 2010; 793-801https://doi.org/10.1115/ICONE18-29820

Abstract

View Articletitled, Adaptive Unbalance Vibration Control of Active Magnetic Bearing Systems for the HTR-10GT

PDF

Topics: Helium , Magnetic bearings , Very high temperature reactors , Vibration control

A Convenient Multi-Model Simulation Technique for Nuclear Reactor System

Jinfeng Peng, Fuyu Zhao, Cheng Liu

ICONE 2010; 803-807https://doi.org/10.1115/ICONE18-29922

Abstract

View Articletitled, A Convenient Multi-Model Simulation Technique for Nuclear Reactor System

PDF

Topics: Nuclear reactors , Simulation , Nonlinear systems , Switches , Transfer functions , Computer software , Matlab

US-APWR Human System Interface System Verification and Validation Program for Digital I&C Design

Satoshi Hanada, Koji Ito, Kenji Mashio

ICONE 2010; 809-814https://doi.org/10.1115/ICONE18-29928

Abstract

View Articletitled, US-APWR Human System Interface System Verification and Validation Program for Digital I&C Design

PDF

Topics: Design , Safety , Pressurized water reactors , Computers , Control systems , Data acquisition systems , Data collection , Ergonomics , Instrumentation , Licensing

Development of a Test Facility and Its Application for Validation and Reliability Testing of Safety-Critical Software

M. Zhao, N. Tailor

ICONE 2010; 815-820https://doi.org/10.1115/ICONE18-29958

Abstract

View Articletitled, Development of a Test Facility and Its Application for Validation and Reliability Testing of Safety-Critical Software

PDF

Topics: Accelerated life testing , Computer software , Safety , Test facilities , Computers , Testing , Hardware , Errors , Plant personnel , Reliability

Development of Nuclear-Specific Coriolis Flowmeters Based on the Straight-Tube Technology

Tao Wang, Yousif Hussain

ICONE 2010; 821-826https://doi.org/10.1115/ICONE18-30055

Abstract

View Articletitled, Development of Nuclear-Specific Coriolis Flowmeters Based on the Straight-Tube Technology

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Topics: Flowmeters , Safety , Calibration , Design , Flow (Dynamics) , Nuclear industry , Testing , Accuracy and precision , ASME Boiler and Pressure Vessel Code , ASME Standards

Mitsubishi Digital I&C System Features for PWR Plant

Shunsuke Ishimoto, Hirokazu Fumon, Masanori Yokoyama

ICONE 2010; 827-834https://doi.org/10.1115/ICONE18-30074

Abstract

View Articletitled, Mitsubishi Digital I&C System Features for PWR Plant

PDF

Topics: Pressurized water reactors , Safety , Design , Monitoring systems , Water , Computer software , Countermeasures , Data acquisition systems , Defense industry , Engineering standards

Study of the Characteristic Response of Pressure Control System in Order to Obtain the Design Parameters of the New Control System MARK VI Turbine in Cofrentes Nuclear Power Plant

Laura Bucho´, Mari´a Jose´ Palomo, Juan Ignacio Vaquer, Bele´n Lo´pez, Gregorio Rui´z, Jose´ Antonio Mora, Gumersindo Verdu´

ICONE 2010; 835-840https://doi.org/10.1115/ICONE18-30095

Abstract

View Articletitled, Study of the Characteristic Response of Pressure Control System in Order to Obtain the Design Parameters of the New Control System MARK VI Turbine in Cofrentes Nuclear Power Plant

PDF

Topics: Control systems , Design , Frequency response , Nuclear power stations , Pressure control , Turbines

Applying Markov Processes for KIC Minimum Configuration Calculation

Ke Tan, Guojin Jiang, Yongbin Sun, Huaqing Peng, Ji Shi

ICONE 2010; 841-844https://doi.org/10.1115/ICONE18-30099

Abstract

View Articletitled, Applying Markov Processes for KIC Minimum Configuration Calculation

PDF

Topics: Markov processes , Teams , Nuclear power stations , Safety , Switches , Accidents , Failure , Finishes , Human factors , Probability

The Incorporation of Task Analysis Into AP1000 Control Rooms Design

Julie Reed, Ruiqi Ma, Zhonghai Li

ICONE 2010; 845-850https://doi.org/10.1115/ICONE18-30183

Abstract

View Articletitled, The Incorporation of Task Analysis Into AP1000 Control Rooms Design

PDF

Topics: Control rooms , Design , Task analysis , Electroosmosis , Emergencies , Maintenance , Risk , Decision making , Electric power generation , Emergency response

Research and Application of Safety Information and Control System of Nuclear Power Station

Liming Zhang, Weijun Huang, Yongbin Sun, Guojin Jiang

ICONE 2010; 851-853https://doi.org/10.1115/ICONE18-30186

Abstract

View Articletitled, Research and Application of Safety Information and Control System of Nuclear Power Station

PDF

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

The Summarization of Power Coordinated Control of Reactor and Turbine

Xiaosheng Dong, Xiaofeng Li, Guangming Liu, Yajie Tian, Guobin Xu, Weijun Huang, Guojin Jiang

ICONE 2010; 855-860https://doi.org/10.1115/ICONE18-30236

Abstract

View Articletitled, The Summarization of Power Coordinated Control of Reactor and Turbine

PDF

Topics: Control systems , Design , Nuclear power stations , Pressurized water reactors , Turbines

Reactor Protection Diversity Requirements and the Typical Solution Base on DCS

Wei-Jun Huang, Ya-Jie Tian, Xiao-Sheng Dong, Li Ming Zhang, Guang-Ming Liu, Guo-Jin Jiang

ICONE 2010; 861-865https://doi.org/10.1115/ICONE18-30237

Abstract

View Articletitled, Reactor Protection Diversity Requirements and the Typical Solution Base on DCS

PDF

Topics: Control systems , Defense industry , Design , Failure , Nuclear power stations , Risk

Measurement of Gamma Radiation Profile Inside a CANDU^® Reactor

S. Yue, B. H. Smith, G. Jonkmans, B. Sur, D. Comeau, D. Taylor

ICONE 2010; 867-871https://doi.org/10.1115/ICONE18-30239

Abstract

View Articletitled, Measurement of Gamma Radiation Profile Inside a CANDU® Reactor

PDF

Topics: Gamma rays , Instrumentation , Radiation (Physics) , Rods , Pressure , Shapes , Silicon

Current Trends in I&C Diversity Implementation

C. Daniel Stiffler, Stephen Seaman

ICONE 2010; 873-876https://doi.org/10.1115/ICONE18-30278

Abstract

View Articletitled, Current Trends in I&C Diversity Implementation

PDF

Topics: Architecture , Defense industry , Instrumentation , Risk

Condition Assessment of NPP Cables Through Indenter Modulus and Break-Elongation Test

Tao Liu, Fei Han, Haining Shi, Xinming Jin

ICONE 2010; 877-881https://doi.org/10.1115/ICONE18-30317

Abstract

View Articletitled, Condition Assessment of NPP Cables Through Indenter Modulus and Break-Elongation Test

PDF

Topics: Cables , Elongation , Nuclear power stations , Accidents , Failure , Heating , Insulation , Radiation (Physics) , Safety , Testing

Safety System and Control System Separation Requirements for ACR-1000™ and Operating CANDU^® Reactors

Sunil Tikku, Gilbert Raiskums, John Harber, Phil Foster

ICONE 2010; 883-892https://doi.org/10.1115/ICONE18-30320

Abstract

View Articletitled, Safety System and Control System Separation Requirements for ACR-1000™ and Operating CANDU® Reactors

PDF

Topics: Control systems , Safety , Separation (Technology) , Control rooms , Computer technology , Computers , Design , Fire , Nuclear reactors

Calibration of Activation Counter by a 2.48 kJ Plasma Focus Device

Sahar Rajabi Moghadam, Fereydoon Abbasi Davani, Babak Shirani Bidabadi

ICONE 2010; 893-896https://doi.org/10.1115/ICONE18-30323

Abstract

View Articletitled, Calibration of Activation Counter by a 2.48 kJ Plasma Focus Device

PDF

Topics: Calibration , Plasmas (Ionized gases) , Neutrons , Silver , Pressure , Anodes , Geiger counters , Neutron sources , Plates (structures)

Integrating Cyber Security Into Nuclear Digital I&C Safety Systems

Deanna Jing Zhang

ICONE 2010; 897-901https://doi.org/10.1115/ICONE18-30345

Abstract

View Articletitled, Integrating Cyber Security Into Nuclear Digital I&C Safety Systems

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Topics: Computer security , Safety , Design , Instrumentation , Nuclear power stations , Security

Digital Instrumentation and Control Systems Upgrades in Current Generation Nuclear Power Plants

Steven A. Arndt

ICONE 2010; 903-910https://doi.org/10.1115/ICONE18-30358

Abstract

View Articletitled, Digital Instrumentation and Control Systems Upgrades in Current Generation Nuclear Power Plants

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Topics: Control systems , Instrumentation , Nuclear power stations , Safety , Design , Computer security , Computer software , Hardware , Licensing , Light water reactors

Research on Distribute Real-Time Database Based on Vxworks

Huwei Li, Duo Li, Huasheng Xiong

ICONE 2010; 911-914https://doi.org/10.1115/ICONE18-30366

Abstract

View Articletitled, Research on Distribute Real-Time Database Based on Vxworks

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Topics: Databases , Computers , Nuclear power stations , Reliability , Control systems , Database management systems , Process control , Safety , Synchronization , System architecture

RCCE-E 2005 Creator of Confidence Between Nuclear Safety Authority, Owner, and Suppliers

J. M. Haure

ICONE 2010; 915-920https://doi.org/10.1115/ICONE18-30369

Abstract

View Articletitled, RCCE-E 2005 Creator of Confidence Between Nuclear Safety Authority, Owner, and Suppliers

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Topics: Safety , Design , Construction , Pressurized water reactors , Regulations , Temperature , Accidents , Blackbody radiation , Control systems , Electrical components