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

Skip Nav Destination

16th International Conference on Nuclear Engineering

May 11–15, 2008

Orlando, Florida, USA

Conference Sponsors:

ISBN:

0-7918-4814-0

In This Volume

Plant Operations, Maintenance, Installations and Life Cycle (46)
Component Reliability and Materials Issues (41)
Advanced Applications of Nuclear Technology (22)
Codes, Standards, Licensing and Regulatory Issues (22)

Volume 1: Plant Operations, Maintenance, Installations and Life Cycle; Component Reliability and Materials Issues; Advanced Applications of Nuclear Technology; Codes, Standards, Licensing and Regulatory Issues

Plant Operations, Maintenance, Installations and Life Cycle

Steam Generator In-Service Inspections at Paks NPP

Miklo´s Do´czi

ICONE 2008; 1-5https://doi.org/10.1115/ICONE16-48063

Abstract

View Articletitled, Steam Generator In-Service Inspections at Paks NPP

PDF

Topics: Boilers , In-service inspection , Nuclear power stations , Eddies (Fluid dynamics) , Eddy currents (Electricity) , Inspection , Condensers (steam plant) , Corrosion , Damage , Eddy current testing

The Main Changes and Consequences by Burnup Extensions in PWRs: Some Recommendations for Negative Plant Performance Issue Limitations

Ivan D. Dobrevski, Neli N. Zaharieva

ICONE 2008; 7-12https://doi.org/10.1115/ICONE16-48099

Abstract

View Articletitled, The Main Changes and Consequences by Burnup Extensions in PWRs: Some Recommendations for Negative Plant Performance Issue Limitations

PDF

Topics: Cladding systems (Building) , Nuclear fuel cycle , Nucleate boiling , Pressurized water reactors , Water , Fuels , Boiling , Corrosion resistance , Nuclear fuels , Boron

Optimal Preventive Maintenance Policy Under a Budget Constraint

Inderjeet Singh, Elmira Popova, Ernie Kee

ICONE 2008; 13-18https://doi.org/10.1115/ICONE16-48107

Abstract

View Articletitled, Optimal Preventive Maintenance Policy Under a Budget Constraint

PDF

Topics: Maintenance , Computation , Design , Optimization

Optimizing Project Prioritization Under Budget Uncertainty

Ali Koc¸, David Morton, Elmira Popova, Stephen Hess, Ernie Kee, Drew Richards

ICONE 2008; 19-26https://doi.org/10.1115/ICONE16-48108

Abstract

View Articletitled, Optimizing Project Prioritization Under Budget Uncertainty

PDF

Topics: Uncertainty , Liabilities , Nuclear industry

An Aging Simulation Model for the Emergency Diesel Generators of Angra 2 by Supplementary Variables

Iona´ Maghali Santos de Oliveira, Paulo Fernando Ferreira Frutuoso e Melo, Marcos Oliveira de Pinho

ICONE 2008; 27-33https://doi.org/10.1115/ICONE16-48112

Abstract

View Articletitled, An Aging Simulation Model for the Emergency Diesel Generators of Angra 2 by Supplementary Variables

PDF

Topics: Diesel generators , Emergencies , Simulation models , Maintenance , Failure , Nuclear power stations , Reliability , Differential equations , Event history analysis , Numerical analysis

Electrical Insulation System Degradation Sensors: Improving Reliability of Power Generation and Distribution

Kenneth S. Watkins

ICONE 2008; 35-39https://doi.org/10.1115/ICONE16-48130

Abstract

View Articletitled, Electrical Insulation System Degradation Sensors: Improving Reliability of Power Generation and Distribution

PDF

Topics: Insulation , Power generation reliability , Sensors , Composite materials , Design , Testing , Electric motors , Electricity (Physics) , Embrittlement , Failure

Statistical Maintenance Optimization Approach at Bruce Power

E. Kevin Doyle, Vesa Tuomi

ICONE 2008; 41-48https://doi.org/10.1115/ICONE16-48135

Abstract

View Articletitled, Statistical Maintenance Optimization Approach at Bruce Power

PDF

Topics: Maintenance , Optimization

Review of the Primary and Secondary Water Chemistry Operation of Paks Nuclear Power Plant From the Point of View of Lifetime Extension

A´rpa´d Doma

ICONE 2008; 49-54https://doi.org/10.1115/ICONE16-48147

Abstract

View Articletitled, Review of the Primary and Secondary Water Chemistry Operation of Paks Nuclear Power Plant From the Point of View of Lifetime Extension

PDF

Topics: Nuclear power stations , Water chemistry , Water , Databases , Service life (Equipment)

Refurbishment of Secondary System and High AVT Water Treatment of Genkai #1 and #2

Jun Manabe, Yasuhiko Shoda, Tatsushi Yamamura, Yuuichirou Kusumoto

ICONE 2008; 55-64https://doi.org/10.1115/ICONE16-48156

Abstract

View Articletitled, Refurbishment of Secondary System and High AVT Water Treatment of Genkai #1 and #2

PDF

Topics: Water treatment , Adhesion , Copper alloys , Heat exchangers , Iron , Coating processes , Coatings , Condensers (steam plant) , Erosion , Feedwater

Thermal Cycle Evaluation for Feedwater Heater Out of Service Condition

Lindsey L. Dziuba, Robert J. Stakenborghs

ICONE 2008; 65-71https://doi.org/10.1115/ICONE16-48187

Abstract

View Articletitled, Thermal Cycle Evaluation for Feedwater Heater Out of Service Condition

PDF

Topics: Cycles , Feedwater , Flow (Dynamics) , Heating , Maintenance , Steam , Trains , Turbines , Acceptance criteria , Complex systems

Comparision of Wind and Nuclear Power Economics

Vern C. Rogers, Gary M. Sandquist, Jay Kunze

ICONE 2008; 73-79https://doi.org/10.1115/ICONE16-48189

Abstract

View Articletitled, Comparision of Wind and Nuclear Power Economics

PDF

Topics: Economics , Nuclear power , Stress , Wind

The Study of Instrument Channel Precision and Application in Nuclear Power Qinshan Joint Venture Company Limited

Tang Yi

ICONE 2008; 81-91https://doi.org/10.1115/ICONE16-48263

Abstract

View Articletitled, The Study of Instrument Channel Precision and Application in Nuclear Power Qinshan Joint Venture Company Limited

PDF

Topics: Instrumentation , Maintenance , Nuclear power

Allowable Load Derivation of Single Angle Members for Small Bore Pipe Supports Welded on 4-Bolt CEA Plate in APR1400

Joon-Ho Lee, Hee-Cheon Choo, Jae-Hwan Bae

ICONE 2008; 93-100https://doi.org/10.1115/ICONE16-48325

Abstract

View Articletitled, Allowable Load Derivation of Single Angle Members for Small Bore Pipe Supports Welded on 4-Bolt CEA Plate in APR1400

PDF

Topics: Pipes , Stress , Design , Plates (structures) , Anchor bolts , Finite element model , Piping systems , Steel , Concretes , Construction

Development of BWR Power Uprate Method Based on “Heat Balance Shift” Concept

Kazuaki Kitou, Masao Chaki, Motoo Aoyama, Kazuhiro Yoshikawa, Hiroshi Sasaki

ICONE 2008; 101-106https://doi.org/10.1115/ICONE16-48343

Abstract

View Articletitled, Development of BWR Power Uprate Method Based on “Heat Balance Shift” Concept

PDF

Topics: Boiling water reactors , Heat , Power uprate , Flow (Dynamics) , High pressure (Physics) , Steam , Turbines , Feedwater , Thermal energy , Temperature

Analyses of Free Span Oxide Layers on SG Tubes of NPP Temelin

A. Hojna, V. Hanus, V. Pisarik, M. Postler, J. Burda, D. Karnik

ICONE 2008; 107-114https://doi.org/10.1115/ICONE16-48390

Abstract

View Articletitled, Analyses of Free Span Oxide Layers on SG Tubes of NPP Temelin

PDF

Topics: Nuclear power stations , Boilers , Feedwater

Development of General-Purpose Software to Analyze the Static Thermal Characteristic of Nuclear Power Generation System

Yoshinobu Nakao, Eiichi Koda, Toru Takahashi

ICONE 2008; 115-120https://doi.org/10.1115/ICONE16-48394

Abstract

View Articletitled, Development of General-Purpose Software to Analyze the Static Thermal Characteristic of Nuclear Power Generation System

PDF

Topics: Computer software , Nuclear power , Heat , Energy / power systems , Algorithms , Boilers , Computers , Steam , Water

Non-Linear BWR Stability Analysis

F. Wehle, A. Schmidt, S. Opel, R. Velten

ICONE 2008; 121-128https://doi.org/10.1115/ICONE16-48395

Abstract

View Articletitled, Non-Linear BWR Stability Analysis

PDF

Topics: Boiling water reactors , Stability , Oscillations , Density , Flow (Dynamics) , Industrial research , Inventions , Nuclear power stations , Waves

Analysis of Pressurized Water Reactor With Pinch, Exergy and Thermoeconomic Methods

Mohammad Hasan Khoshgoftar Manesh, Majid Amidpour

ICONE 2008; 129-138https://doi.org/10.1115/ICONE16-48429

Abstract

View Articletitled, Analysis of Pressurized Water Reactor With Pinch, Exergy and Thermoeconomic Methods

PDF

Topics: Exergy , Pinch effect , Pressurized water reactors , Thermoeconomics , Power stations , Computer software , Design , Energy conservation , Nuclear power stations , Simulation

New Graphical Methodology for Energy Integration in Nuclear Steam Power Plant

Mohammad Hasan Khoshgoftar Manesh, Majid Amidpour

ICONE 2008; 139-155https://doi.org/10.1115/ICONE16-48432

Abstract

View Articletitled, New Graphical Methodology for Energy Integration in Nuclear Steam Power Plant

PDF

Topics: Thermal power stations , Exergy , Simulation , Design , Energy levels (Quantum mechanics) , Pinch effect , Power stations , Chemical processes , Composite materials , Computer software

Evaluation of Coupling Desalination With PWR Nuclear Power Plant With Pinch, Exergy and Thermoeconomic Analysis

Mohammad Hasan Khoshgoftar Manesh, Majid Amidpour, Ali Farhadi, Gholam Reza Salehi

ICONE 2008; 157-170https://doi.org/10.1115/ICONE16-48441

Abstract

View Articletitled, Evaluation of Coupling Desalination With PWR Nuclear Power Plant With Pinch, Exergy and Thermoeconomic Analysis

PDF

Topics: Exergy , Nuclear power stations , Pinch effect , Pressurized water reactors , Thermoeconomics , Simulation , Design , Energy levels (Quantum mechanics) , Power stations , Chemical processes

Low Boron Level Loading Pattern

Cenk Gu¨ler, Jeffery A. Brown

ICONE 2008; 171-175https://doi.org/10.1115/ICONE16-48473

Abstract

View Articletitled, Low Boron Level Loading Pattern

PDF

Topics: Boron , Cycles , Design , Pressurized water reactors , Chemistry , Coolants , Economics , Fuels , Gadolinium , Manufacturing

Cable Aging Assessment and Condition Monitoring Using Line Resonance Analysis (LIRA)

Gary J. Toman, Paolo F. Fantoni

ICONE 2008; 177-186https://doi.org/10.1115/ICONE16-48523

Abstract

View Articletitled, Cable Aging Assessment and Condition Monitoring Using Line Resonance Analysis (LIRA)

PDF

Topics: Cables , Condition monitoring , Resonance , Insulation , Signals

Thermalhydraulic Analysis of the Steam Generator Design for the 700 MWe Indian Nuclear Power Plant

Benny John, John M. Pietralik

ICONE 2008; 187-195https://doi.org/10.1115/ICONE16-48531

Abstract

View Articletitled, Thermalhydraulic Analysis of the Steam Generator Design for the 700 MWe Indian Nuclear Power Plant

PDF

Topics: Boilers , Design , Nuclear power stations , Flow (Dynamics) , Steam , Feedwater , Geometry , Heat transfer , Heavy water reactors , Nuclear power

Analysis and Strategy of Ageing and Ageing Management for Steam Generator in 300MWe NPP

Dong Ning, Kefeng Zhang, Weida Yao

ICONE 2008; 197-207https://doi.org/10.1115/ICONE16-48561

Abstract

View Articletitled, Analysis and Strategy of Ageing and Ageing Management for Steam Generator in 300MWe NPP

PDF

Topics: Boilers , Nuclear power stations , Safety , Design , Errors , Failure , Maintenance , Manufacturing , Service life (Equipment) , Wear

Human Factors Verification and Validation: Tecnatom’s Experience

Pedro Trueba Alonso, Lui´s Ferna´ndez Illobre, Alfonso Jime´nez Ferna´ndez-Sesma, Fernando Ortega Pascual

ICONE 2008; 209-216https://doi.org/10.1115/ICONE16-48568

Abstract

View Articletitled, Human Factors Verification and Validation: Tecnatom’s Experience

PDF

Topics: Human factors , Design , Nuclear power stations , Ergonomics , Control rooms , Data collection , Integrated systems , Task analysis

Technical Development for IASCC Irradiation Experiments at the JMTR

Akira Shibata, Junichi Nakano, Masao Ohmi, Kazuo Kawamata, Takashi Saito, Kouji Hayashi, Junichi Saito, Tetsuya Nakagawa, Takashi Tsukada

ICONE 2008; 217-224https://doi.org/10.1115/ICONE16-48588

Abstract

View Articletitled, Technical Development for IASCC Irradiation Experiments at the JMTR

PDF

Topics: Irradiation (Radiation exposure) , Fluence (Radiation measurement) , Neutrons , Fracture (Materials) , Light water reactors , Welding , Chemistry , Elongation , Machinery , Materials testing

Seismic Response Analysis of Reactor Coolant Pump in Nuclear Power Plant

Zhaohui Ren, Hui Ma, He Li, Guiqiu Song, Wenjian Zhou

ICONE 2008; 225-230https://doi.org/10.1115/ICONE16-48637

Abstract

View Articletitled, Seismic Response Analysis of Reactor Coolant Pump in Nuclear Power Plant

PDF

Topics: Nuclear power stations , Nuclear reactor coolants , Pumps , Vibration , Coolants , Damage , Earthquakes , Emission spectroscopy , Security , Spectroscopy

Development of Significance Determination Process in Japan

Yusuke Kasagawa, Masajiro Sugawara, Tsuyoshi Uchida, Katsunori Ogura, Masahiro Yamashita

ICONE 2008; 231-239https://doi.org/10.1115/ICONE16-48676

Abstract

View Articletitled, Development of Significance Determination Process in Japan

PDF

Topics: Boiling water reactors , Condensers (steam plant) , Containment , Damage , Design , Ice , Inspection , Light water reactors , Maintenance , Nuclear industry

Development of an Evaluation Tool of Radiation Dose Rate in Primary Containment Vessel for Hamaoka BWR Plants

Hiromitsu Inagaki

ICONE 2008; 241-244https://doi.org/10.1115/ICONE16-48688

Abstract

View Articletitled, Development of an Evaluation Tool of Radiation Dose Rate in Primary Containment Vessel for Hamaoka BWR Plants

PDF

Topics: Boiling water reactors , Containment vessels , Radiation (Physics) , Water chemistry

Chiller Condenser Service Water Cooling Valve Maintenance

Ken Boughton, Paul N. Hansen

ICONE 2008; 245-252https://doi.org/10.1115/ICONE16-48718

Abstract

View Articletitled, Chiller Condenser Service Water Cooling Valve Maintenance

PDF

Topics: Condensers (steam plant) , Cooling , Maintenance , Valves , Water , Flow control valves , Refrigeration , Stress , Actuators , Control rooms

Autoregressive Multivariate Analysis of BWR Bistable Flow

Rogelio Castillo-Dura´n, Javier Ortiz-Villafuerte, Raymundo Go´mez-Herrera, Gabriel Calleros-Micheland

ICONE 2008; 253-259https://doi.org/10.1115/ICONE16-48730

Abstract

View Articletitled, Autoregressive Multivariate Analysis of BWR Bistable Flow

PDF

Topics: Boiling water reactors , Flow (Dynamics) , Signals , Stress , Computer software , Dynamics (Mechanics) , Failure , Fluctuations (Physics) , Noise (Sound) , Nuclear power stations

Relational Design Method for New Reactor Licensing

J. K. August, Joe Hunter

ICONE 2008; 261-278https://doi.org/10.1115/ICONE16-48785

Abstract

View Articletitled, Relational Design Method for New Reactor Licensing

PDF

Topics: Design methodology , Licensing , Design , Errors , Nuclear construction

Dresden Units 2 and 3 Isolation Condenser Waterhammer Prevention During Restart Operations

John Freeman, Kevin Ramsden, Paul Kovacs

ICONE 2008; 279-287https://doi.org/10.1115/ICONE16-48808

Abstract

View Articletitled, Dresden Units 2 and 3 Isolation Condenser Waterhammer Prevention During Restart Operations

PDF

Topics: Condensers (steam plant) , Pipes , Condensed matter , Damage , Transients (Dynamics) , Hydraulic transients , Nuclear reactors , Stress , Valves

Development of Atlas of Defects of Steam Generators Heat Exchanging Tubes of NPPs With WWER and Analysis of Testing Results

Murat Bakirov, Sergei Chubarov, Nikolay Trunov

ICONE 2008; 289-296https://doi.org/10.1115/ICONE16-48815

Abstract

View Articletitled, Development of Atlas of Defects of Steam Generators Heat Exchanging Tubes of NPPs With WWER and Analysis of Testing Results

PDF

Topics: Boilers , Heat , Nuclear power stations , Testing , Algorithms , Eddies (Fluid dynamics) , Eddy current testing , Eddy currents (Electricity) , Inspection , Metals

AP1000 Fuel Design and Core Operations

R. Wade Miller

ICONE 2008; 297-304https://doi.org/10.1115/ICONE16-48888

Abstract

View Articletitled, AP1000 Fuel Design and Core Operations

PDF

Topics: Design , Fuels , Manufacturing , Plant design

Development of a Next Generation Canister Sipping System

Richard E. Longenecker, John D. Wood

ICONE 2008; 305-311https://doi.org/10.1115/ICONE16-48894

Abstract

View Articletitled, Development of a Next Generation Canister Sipping System

PDF

Topics: Computer software , Decontamination , Design , Electronics , Fuels , Instrumentation , Leakage , Sensors , Storage , Weight (Mass)

Development and Application of Technologies Maintenance of a Lifetime and Safety the NPP Components

G. V. Arkadov, A. F. Getman, A. I. Usanov

ICONE 2008; 313-319https://doi.org/10.1115/ICONE16-48904

Abstract

View Articletitled, Development and Application of Technologies Maintenance of a Lifetime and Safety the NPP Components

PDF

Topics: Maintenance , Nuclear power stations , Safety , Pipelines , In-service inspection , Reliability , Service life (Equipment) , Fracture (Materials) , Mechanical properties , Steel

Overview of EDF Life Cycle Management and Nuclear Asset Management Methodology and Tools

P. Hai¨k, K. Fessart, E. Remy, J. Lonchampt

ICONE 2008; 321-331https://doi.org/10.1115/ICONE16-48911

Abstract

View Articletitled, Overview of EDF Life Cycle Management and Nuclear Asset Management Methodology and Tools

PDF

Topics: Life cycle management , Computer software , Maintenance , Decision making , Durability , Economics , Nuclear power plant maintenance , Optimization , Pressurized water reactors , Safety

Fuel Assembly Instrument Tube Tie-Rods

John D. Wood, Larry Montgomery

ICONE 2008; 333-339https://doi.org/10.1115/ICONE16-48913

Abstract

View Articletitled, Fuel Assembly Instrument Tube Tie-Rods

PDF

Topics: Fuels , Instrumentation , Manufacturing , Tie rods , Nozzles , Spent nuclear fuels , Design , Stainless steel , Stress , Chemistry

ACR-1000^® Plant Layout

Brian Pedherney, Medhat Elgohary, Justin Alizadeh

ICONE 2008; 341-349https://doi.org/10.1115/ICONE16-48919

Abstract

View Articletitled, ACR-1000<sup>®</sup> Plant Layout

PDF

Topics: Plant layout , Design , Feedback , Construction , Engineering disciplines , Innovation , Maintenance , Nuclear power , Nuclear power stations , Pressure

Increased Concern for Degradation of Upper Steam Drum Internals Leading to Monitoring and Modifications Considerations

David P. Popovich, M. H. Hu, Jonathan L. Barkich, Peter R. Nelson

ICONE 2008; 351-359https://doi.org/10.1115/ICONE16-48938

Abstract

View Articletitled, Increased Concern for Degradation of Upper Steam Drum Internals Leading to Monitoring and Modifications Considerations

PDF

Topics: Steam , Boilers , Inspection , Surveillance , Corrosion , Failure mechanisms , Flow (Dynamics) , Particulate matter , Separation (Technology) , Acceptance criteria

Warranty Test for a High-Pressure Turbine Retrofit Using Process Data Reconciliation in Accordance With VDI 2048

Magnus Langenstein, Steffen Riehm, Jan Hansen-Schmidt

ICONE 2008; 361-364https://doi.org/10.1115/ICONE16-48940

Abstract

View Articletitled, Warranty Test for a High-Pressure Turbine Retrofit Using Process Data Reconciliation in Accordance With VDI 2048

PDF

Topics: High pressure (Physics) , Turbines , Instrumentation , Nuclear power stations , Thermal reactors

Flow-Induced Vibration Model for Steam Generator Tubes in Two-Phase Flow

Njuki W. Mureithi, Soroush Shahriary, Michel J. Pettigrew

ICONE 2008; 365-374https://doi.org/10.1115/ICONE16-48942

Abstract

View Articletitled, Flow-Induced Vibration Model for Steam Generator Tubes in Two-Phase Flow

PDF

Topics: Boilers , Flow-induced vibrations , Two-phase flow , Flow (Dynamics) , Fluids , Stability , Vibration , Computation , Databases , Engineering simulation

Radiation Protection Technician Two-Year Associates of Applied Science Curriculum for National Implementation

William H. Miller, David Jonassen, Rose Marra, Matthew Schmidt, Matthew Easter, Ioan Gelu Ionas, Gayla M. Neumeyer, Randy Etter, Bruce Meffert, Christopher C. Graham

ICONE 2008; 375-380https://doi.org/10.1115/ICONE16-48952

Abstract

View Articletitled, Radiation Protection Technician Two-Year Associates of Applied Science Curriculum for National Implementation

PDF

Topics: Radiation (Physics) , Nuclear power stations , Collaboration , Internships , Nuclear industry , Public utilities , Students

Development of Full Scale Reactor Coolant Pump Thrust Bearing Test System and Qualification Process for Retrofit Thrust Bearing Oil Seal With Commercial Grade Components

Jason Sinkhorn, William Mendez

ICONE 2008; 381-384https://doi.org/10.1115/ICONE16-48956

Abstract

View Articletitled, Development of Full Scale Reactor Coolant Pump Thrust Bearing Test System and Qualification Process for Retrofit Thrust Bearing Oil Seal With Commercial Grade Components

PDF

Topics: Nuclear reactor coolants , Pumps , Thrust bearings , Bearings , Computers , Design , Engineering prototypes , Experimental design , Leakage , Stress

An Equipment Reliability Strategy and Maintenance Program for Improving the Reliability of Cranes at Commercial Nuclear Power Facilities

Jeffrey B. Kriner, Bradford P. Lytle, John C. Lauri

ICONE 2008; 384-393https://doi.org/10.1115/ICONE16-48467

Abstract

View Articletitled, An Equipment Reliability Strategy and Maintenance Program for Improving the Reliability of Cranes at Commercial Nuclear Power Facilities

PDF

Topics: Cranes , Maintenance , Nuclear power , Reliability , Electricity (Physics) , Equipment performance , Feedback , Licensing , Mechanical engineers , Nuclear power stations

Component Reliability and Materials Issues

Stress Rupture Characteristics of Zirconium Alloy Cladding Under Closed-End Internal Pressurization

B. Marple, Y. J. Song, S. Gollapudi, K. L. Murty, I. Charit

ICONE 2008; 385-388https://doi.org/10.1115/ICONE16-48006

Abstract

View Articletitled, Stress Rupture Characteristics of Zirconium Alloy Cladding Under Closed-End Internal Pressurization

PDF

Topics: Cladding systems (Building) , Rupture , Stress , Zirconium alloys , Creep , Alloys , Deformation , Elongation , Nuclear reactors , Temperature

Simulations of Metal Oxidation in LBE at a Mesoscopic Level

Taide Tan, Yitung Chen

ICONE 2008; 389-403https://doi.org/10.1115/ICONE16-48025

Abstract

View Articletitled, Simulations of Metal Oxidation in LBE at a Mesoscopic Level

PDF

Topics: Engineering simulation , Mesoscopic systems , Metals , Oxidation , Simulation , Diffusion (Physics) , Diffusion processes , Grain boundaries , Ionization , Ions

Evaluation of Cross-Weld Properties of Austenitic Stainless Steels Before and After PWHT

M. M. Ibrahim, H. G. Mohamed, Y. E. Tawfik, Ibrahim Taha

ICONE 2008; 405-414https://doi.org/10.1115/ICONE16-48043

Abstract

View Articletitled, Evaluation of Cross-Weld Properties of Austenitic Stainless Steels Before and After PWHT

PDF

Topics: Stainless steel , Tensile strength , Ductility , Gas tungsten arc welding , Heat treating (Metalworking) , Piping systems , Plates (structures) , Residual stresses , Steel , Temperature

Phosphate Ions: Does Exposure Lead to Degradation of Cementitious Materials?

Dan J. Naus, Herman L. Graves, III, Catherine H. Mattus, Leslie R. Dole

ICONE 2008; 415-421https://doi.org/10.1115/ICONE16-48051

Abstract

View Articletitled, Phosphate Ions: Does Exposure Lead to Degradation of Cementitious Materials?

PDF

Topics: Cements (Building materials) , Ions , Concretes , Durability , Nuclear power stations , Soil , Groundwater , Reinforced concrete , Water

Weld Material Investigations of a WWER-440 Reactor Pressure Vessel: Results From the First Trepan Taken From the Former Greifswald NPP

Udo Rindelhardt, Hans-Werner Viehrig, Joerg Konheiser, Jan Schuhknecht

ICONE 2008; 423-431https://doi.org/10.1115/ICONE16-48070

Abstract

View Articletitled, Weld Material Investigations of a WWER-440 Reactor Pressure Vessel: Results From the First Trepan Taken From the Former Greifswald NPP

PDF

Topics: Nuclear power stations , Reactor vessels , Fluence (Radiation measurement) , Neutrons , Brittleness , Temperature , Cycles , Fracture toughness , Metals , Welded joints

A Point Process Model for Piping Failure Frequency Analysis Using OPDE Data

X.-X. Yuan, M. D. Pandey, J. Riznic

ICONE 2008; 433-441https://doi.org/10.1115/ICONE16-48078

Abstract

View Articletitled, A Point Process Model for Piping Failure Frequency Analysis Using OPDE Data

PDF

Topics: Failure , Pipes , Databases , Failure data , Nuclear power stations , Probabilistic risk assessment , Risk-informed in-service inspection

Corrosion Behavior of Carbon Steel for the Overpack in the Groundwater Containing Bicarbonate Ions

Toshiyasu Nishimura, Junpha Dong

ICONE 2008; 443-448https://doi.org/10.1115/ICONE16-48081

Abstract

View Articletitled, Corrosion Behavior of Carbon Steel for the Overpack in the Groundwater Containing Bicarbonate Ions

PDF

Topics: Carbon steel , Corrosion , Groundwater , Ions

Experiments on Eurofer Steel Corrosion by Pb-16Li

Alessandro Gessi, Antonio Aiello, Gianluca Benamati

ICONE 2008; 449-473https://doi.org/10.1115/ICONE16-48167

Abstract

View Articletitled, Experiments on Eurofer Steel Corrosion by Pb-16Li

PDF

Topics: Corrosion , Helium , Liquid alloys , Liquid metals , Lithium , Metallurgical analysis , Steel , Steel corrosion , Temperature , Weight (Mass)

On Nanoceramic Fuel for Perspective Nuclear Reactors

Pavel N. Alekseev, Alexander A. Proshkin, Alexander L. Shimkevich

ICONE 2008; 475-481https://doi.org/10.1115/ICONE16-48177

Abstract

View Articletitled, On Nanoceramic Fuel for Perspective Nuclear Reactors

PDF

Topics: Fuels , Nuclear reactors , Oxide ceramics

Remotely Operated Equipments for In-Vessel Inspection in BWRs

Yasuhiro Yuguchi, Katsuhiko Naruse, Mitsuaki Shimamura, Takao Sato, Takeshi Maehara, Hiroshi Iimori

ICONE 2008; 483-490https://doi.org/10.1115/ICONE16-48199

Abstract

View Articletitled, Remotely Operated Equipments for In-Vessel Inspection in BWRs

PDF

Topics: Boiling water reactors , Inspection , Vessels , Testing , Measurement systems , Vehicles , Engineering prototypes , Jet pumps , Nuclear power stations , Stress corrosion cracking

Laser Peening Systems for Preventive Maintenance Against Stress Corrosion Cracking in Nuclear Power Reactors

Takuya Uehara, Masaki Yoda, Yuji Sano, Naruhiko Mukai, Itaru Chida, Hiromi Kato

ICONE 2008; 491-497https://doi.org/10.1115/ICONE16-48202

Abstract

View Articletitled, Laser Peening Systems for Preventive Maintenance Against Stress Corrosion Cracking in Nuclear Power Reactors

PDF

Topics: Laser hardening , Maintenance , Nuclear reactors , Stress corrosion cracking , Lasers , Irradiation (Radiation exposure) , Mirrors , Control systems , Engineering prototypes , Fibers

Fundamental Mechanisms of Component Degradation by Corrosion in Nuclear Power Plants of Russian Design

G. Saji, V. A. Yurmanov, V. I. Baranenko, V. A. Fedorova, G. Karzov, B. T. Timofeev

ICONE 2008; 499-518https://doi.org/10.1115/ICONE16-48308

Abstract

View Articletitled, Fundamental Mechanisms of Component Degradation by Corrosion in Nuclear Power Plants of Russian Design

PDF

Topics: Corrosion , Design , Nuclear power stations , Water chemistry , Boiling water reactors , Pressurized water reactors , Boilers , Pipes , Potassium , Welding

Assurance of Seismic Safety by Defense-in-Depth and Safety Goals: Lessons Learned From the Chuˆetsu-Oki Earthquake (2007)

G. Saji

ICONE 2008; 519-532https://doi.org/10.1115/ICONE16-48309

Abstract

View Articletitled, Assurance of Seismic Safety by Defense-in-Depth and Safety Goals: Lessons Learned From the Chuˆetsu-Oki Earthquake (2007)

PDF

Topics: Defense industry , Earthquakes , Safety

The Study on the Applicability of Laser Surface Modification Technology to Irradiated Stainless Steel

Masatoshi Sato, Masanori Kanno, Kiyotomo Nakata, Hidenori Takahashi, Hiroshi Sakamoto

ICONE 2008; 533-538https://doi.org/10.1115/ICONE16-48312

Abstract

View Articletitled, The Study on the Applicability of Laser Surface Modification Technology to Irradiated Stainless Steel

PDF

Topics: Lasers , Stainless steel , Helium , Boiling water reactors , Bubbles , Heat , Stress corrosion cracking , Welding , Aluminum , Boron

Application of Magnetic Stir Welding to Dissimilar Metal Structural Weld Overlay

Takeshi Yoshida, Takaaki Matsuoka, Yuta Uchida, Takashi Hirano

ICONE 2008; 539-546https://doi.org/10.1115/ICONE16-48319

Abstract

View Articletitled, Application of Magnetic Stir Welding to Dissimilar Metal Structural Weld Overlay

PDF

Topics: Metals , Overlays (Materials engineering) , Welding , Municipal solid wastes , Alloys , Fracture (Materials) , Stainless steel , Sulfur , Welded joints , Base metals

Development of Underwater Laser Cladding and Underwater Laser Seal Welding Techniques for Reactor Components (III)

Masataka Tamura, Yoshinobu Makino, Takehisa Hino, Shohei Kawano, Wataru Kouno, Keiji Matsunaga

ICONE 2008; 547-550https://doi.org/10.1115/ICONE16-48326

Abstract

View Articletitled, Development of Underwater Laser Cladding and Underwater Laser Seal Welding Techniques for Reactor Components (III)

PDF

Topics: Cladding systems (Building) , Lasers , Welding , Laser welding , Maintenance , Nuclear power stations , Radiation (Physics) , Stress corrosion cracking , Water

The Influence of the Grain Structure Size on Microstructurally Small Cracks

I. Simonovski, L. Cizelj

ICONE 2008; 551-558https://doi.org/10.1115/ICONE16-48340

Abstract

View Articletitled, The Influence of the Grain Structure Size on Microstructurally Small Cracks

PDF

Topics: Crystals , Fracture (Materials) , Plasticity

Study on Chemical Reactivity Control of Liquid Sodium: Development of Nano-Fluid and Its Property and Applicability to FBR Plant

Jun-Ichi Saito, Kuniaki Ara, Ken-Ichiro Sugiyama, Hiroshi Kitagawa, Haruyuki Nakano, Kan Ogata, Naoki Yoshioka

ICONE 2008; 559-563https://doi.org/10.1115/ICONE16-48367

Abstract

View Articletitled, Study on Chemical Reactivity Control of Liquid Sodium: Development of Nano-Fluid and Its Property and Applicability to FBR Plant

PDF

Topics: Nanofluids , Nanoparticles , Sodium

Reliability of Water Jet Peening as Residual Stress Improvement Method for Alloy 600 PWSCC Mitigation

Koji Okimura, Takao Konno, Marekazu Narita, Takahiro Ohta, Masahiko Toyoda

ICONE 2008; 565-570https://doi.org/10.1115/ICONE16-48375

Abstract

View Articletitled, Reliability of Water Jet Peening as Residual Stress Improvement Method for Alloy 600 PWSCC Mitigation

PDF

Topics: Alloys , Reliability , Shot peening , Stress , Water , Compressive stress , Countermeasures , Instrumentation , Lasers , Metals

PWSCC of Nickel Base Alloys in Vapor Phase Environment of Pressurizer

Takao Tsuruta, Kenji Sato, Seiji Asada, Takaaki Kobayashi, Koji Okimura, Nariyasu Matsubara

ICONE 2008; 571-573https://doi.org/10.1115/ICONE16-48377

Abstract

View Articletitled, PWSCC of Nickel Base Alloys in Vapor Phase Environment of Pressurizer

PDF

Topics: Alloys , Nickel , Vapors , Liquid films , Water , Chemistry , Metals , Crack propagation , Fracture (Materials) , Pressurized water reactors

Application of Outer Surface Irradiated Laser Stress Improvement Process (L-SIP) to Pressurizer as Residual Stress Improvement Method for Alloy 600 PWSCC Mitigation

Takeshi Ueda, Koji Okimura, Kazuhiro Wakabayashi, Takashi Akaba, Kazuhiko Kamo, Takahiro Ohta

ICONE 2008; 575-579https://doi.org/10.1115/ICONE16-48379

Abstract

View Articletitled, Application of Outer Surface Irradiated Laser Stress Improvement Process (L-SIP) to Pressurizer as Residual Stress Improvement Method for Alloy 600 PWSCC Mitigation

PDF

Topics: Alloys , Lasers , Stress , Pipes , Steel , Welded joints , Compressive stress , Countermeasures , Laser beams , Nozzles

Recirculation Pump Speed Control System Upgrades in Nuclear Boiling Water Reactors

James W. Morgan

ICONE 2008; 581-593https://doi.org/10.1115/ICONE16-48411

Abstract

View Articletitled, Recirculation Pump Speed Control System Upgrades in Nuclear Boiling Water Reactors

PDF

Topics: Boiling water reactors , Control systems , Pumps , Reliability , Design , Engines , Flow control , Flow control valves , Generators , Motors

New Metallic Gaskets Qualification: Resistance to Accident and Normal Conditions in TN International Casks

Re´gis Marlier, Herve´ Issard

ICONE 2008; 595-605https://doi.org/10.1115/ICONE16-48418

Abstract

View Articletitled, New Metallic Gaskets Qualification: Resistance to Accident and Normal Conditions in TN International Casks

PDF

Topics: Accidents , Gaskets , Displacement , Storage , Particulate matter , Temperature , Compression , Design , Fire , High temperature

Residual Stress Fields Under Different Clamping Conditions in Circumferentially Welded Thin-Walled Cylinders

Afzaal M. Malik, Ejaz M. Qureshi, Naeem Ullah Dar, Iqbal Khan

ICONE 2008; 607-615https://doi.org/10.1115/ICONE16-48422

Abstract

View Articletitled, Residual Stress Fields Under Different Clamping Conditions in Circumferentially Welded Thin-Walled Cylinders

PDF

Topics: Cylinders , Residual stresses , Simulation , Stress , Thermomechanics , Welding

Development of Low-Activation Design Method for Reduction of Radioactive Waste Below Clearance Level

Ken-Ichi Kimura, Akira Hasegawa, Katsumi Hayashi, Mikio Uematsu, Tomohiro Ogata, Takao Tanosaki, Ryoetsu Yoshino, Mituru Sato, Minoru Saito, Masaharu Kinno

ICONE 2008; 617-626https://doi.org/10.1115/ICONE16-48484

Abstract

View Articletitled, Development of Low-Activation Design Method for Reduction of Radioactive Waste Below Clearance Level

PDF

Topics: Clearances (Engineering) , Design methodology , Radioactive wastes , Concretes , Databases , Radioactivity , Raw materials , Cements (Adhesives) , Reinforced concrete , Steel

Characterization and Structural Integrity Tests of Ex-Service Steam Generator Tubes

Sandra Pagan, Xinjian Duan, Michael J. Kozluk, Brian Mills, Guylaine Goszczynski

ICONE 2008; 627-632https://doi.org/10.1115/ICONE16-48505

Abstract

View Articletitled, Characterization and Structural Integrity Tests of Ex-Service Steam Generator Tubes

PDF

Topics: Boilers , Energy generation , Mechanical properties

Research and Analysis on Damage of Fretting Wear and Fretting Fatigue for Components in NPPs

Dong Ning, Min Zhang, Yongchen Xie, Yinbiao He, Weida Yao

ICONE 2008; 633-640https://doi.org/10.1115/ICONE16-48516

Abstract

View Articletitled, Research and Analysis on Damage of Fretting Wear and Fretting Fatigue for Components in NPPs

PDF

Topics: Damage , Fatigue , Nuclear power stations , Wear

Effect of Orientation on Mechanical Behavior of an Extruded Al Alloy

M. A. Malik, I. Salam, W. Muhammad

ICONE 2008; 641-647https://doi.org/10.1115/ICONE16-48548

Abstract

View Articletitled, Effect of Orientation on Mechanical Behavior of an Extruded Al Alloy

PDF

Topics: Aluminum alloys , Extruding , Mechanical behavior , Mechanical properties , Reliability , Yield strength , Cylinders , Elongation , Fracture (Materials) , Fracture (Process)

Mitigation of Stress Corrosion Cracking in Nuclear Weldments Using Low Plasticity Burnishing

Jeremy E. Scheel, Douglas J. Hornbach, Paul S. Prevey

ICONE 2008; 649-656https://doi.org/10.1115/ICONE16-48597

Abstract

View Articletitled, Mitigation of Stress Corrosion Cracking in Nuclear Weldments Using Low Plasticity Burnishing

PDF

Topics: Plasticity , Stress corrosion cracking , Alloys , Residual stresses , Stainless steel , Boiling water reactors , Compression , Pressurized water reactors , Stress , Computer numerical control machine tools

Flow-Accelerated Corrosion Susceptibility Prediction of Recirculating Steam Generator Internals

John M. Pietralik, Kevin L. Heppner

ICONE 2008; 657-664https://doi.org/10.1115/ICONE16-48630

Abstract

View Articletitled, Flow-Accelerated Corrosion Susceptibility Prediction of Recirculating Steam Generator Internals

PDF

Topics: Boilers , Corrosion , Flow (Dynamics) , Chemistry , Water chemistry , Carbon steel , Computers , Design , Equilibrium (Physics) , Failure

Development of the Optimized Fatigue Analysis Procedure to Evaluate Design Life for APR1400

Jaegon Lee, Taesoon Kim, Chankook Moon, Kwanghan Lee

ICONE 2008; 665-670https://doi.org/10.1115/ICONE16-48659

Abstract

View Articletitled, Development of the Optimized Fatigue Analysis Procedure to Evaluate Design Life for APR1400

PDF

Topics: Design , Fatigue analysis , Fatigue , Fatigue design , Nozzles , Nuclear power stations , ASME Standards , Boilers , Coolants , Failure mechanisms

Results on Attenuation of Neutron Embrittlement Effects

Milan Brumovsky´, Milosˇ Kytka, William Server, Naoki Soneda, Jack Spanner

ICONE 2008; 671-678https://doi.org/10.1115/ICONE16-48710

Abstract

View Articletitled, Results on Attenuation of Neutron Embrittlement Effects

PDF

Topics: Embrittlement , Neutrons , Copper , Steel , ASTM International , Fluence (Radiation measurement) , Fracture toughness , Atoms , Damage , Irradiation (Radiation exposure)

Current Issues in Operated WWER Type RPVs

Milan Brumovsky´, Milos Kytka

ICONE 2008; 679-683https://doi.org/10.1115/ICONE16-48713

Abstract

View Articletitled, Current Issues in Operated WWER Type RPVs

PDF

Topics: Cladding systems (Building) , Design , Embrittlement , Engineering standards , Fracture toughness , Irradiation (Radiation exposure) , Nickel , Nuclear power stations , Pressurized water reactors , Radiation (Physics)

The Effect of Inspection Uncertainties in Predicting the Probability of Leak of Steam Generator Tubing Due to Pitting

M. D. Pandey, S. V. Datta, D. Komljenovic

ICONE 2008; 685-693https://doi.org/10.1115/ICONE16-48729

Abstract

View Articletitled, The Effect of Inspection Uncertainties in Predicting the Probability of Leak of Steam Generator Tubing Due to Pitting

PDF

Topics: Boilers , Inspection , Leakage , Probability , Tubing , Uncertainty , Accounting , Corrosion , Eddies (Fluid dynamics) , Eddy currents (Electricity)

Management of Component Fatigue in CANDU Stations for Life Extension

M. Yetisir, G. L. Stevens, S. Robertson

ICONE 2008; 695-701https://doi.org/10.1115/ICONE16-48757

Abstract

View Articletitled, Management of Component Fatigue in CANDU Stations for Life Extension

PDF

Topics: Fatigue , Life extension , Design , Transients (Dynamics) , Boiling water reactors , Pressurized water reactors , Licensing , Nuclear power stations , Oxygen , Power stations

Susceptibility of Intergranular Corrosion for Extra High Purity Austenitic Stainless Steel in Nitric Acid

Ikuo Ioka, Chiaki Kato, Kiyoshi Kiuchi, Junpei Nakayama

ICONE 2008; 703-707https://doi.org/10.1115/ICONE16-48776

Abstract

View Articletitled, Susceptibility of Intergranular Corrosion for Extra High Purity Austenitic Stainless Steel in Nitric Acid

PDF

Topics: Corrosion , Stainless steel , Alloys , Boiling , Boron , Corrosion resistance , Etching , Grain boundaries , Ions , Melting

Investigation of Effect of Pre-Strain on Very High-Cycle Fatigue Strength of Austenitic Stainless Steels

Takeshi Ogawa, Motoki Nakane, Kiyotaka Masaki, Shota Hashimoto, Yasuo Ochi, Kyoichi Asano

ICONE 2008; 709-715https://doi.org/10.1115/ICONE16-48811

Abstract

View Articletitled, Investigation of Effect of Pre-Strain on Very High-Cycle Fatigue Strength of Austenitic Stainless Steels

PDF

Topics: High cycle fatigue , Stainless steel , Fatigue testing , Fatigue strength , Fracture (Materials) , Compression , Fatigue cracks , Machining , Nuclear power stations , Structural elements (Construction)

Component Reliability Considerations for New Designs and Extended Operation of Boiling Water Reactor (BWRs)

E. Kiss

ICONE 2008; 717-721https://doi.org/10.1115/ICONE16-48864

Abstract

View Articletitled, Component Reliability Considerations for New Designs and Extended Operation of Boiling Water Reactor (BWRs)

PDF

Topics: Boiling water reactors , Reliability , Alloy steel , Alloys , Irradiation (Radiation exposure) , Nickel , Stainless steel , Carbon , Corrosion , Design

Bayesian Prediction for the Gumbel Distribution Applied to Feeder Pipe Thicknesses

Fred M. Hoppe, Lin Fang

ICONE 2008; 723-729https://doi.org/10.1115/ICONE16-48871

Abstract

View Articletitled, Bayesian Prediction for the Gumbel Distribution Applied to Feeder Pipe Thicknesses

PDF

Topics: Pipes , Inspection , Chain , Fitness-for-service , Nuclear power stations , Probability , Radiation (Physics) , Wall thickness

Realistically Improved Finite Element Analysis of Spring Supports in a Nuclear Fuel Spacer Grid

Jae-Yong Kim, Kyung-Ho Yoon, Hyung-Kyu Kim

ICONE 2008; 731-736https://doi.org/10.1115/ICONE16-48957

Abstract

View Articletitled, Realistically Improved Finite Element Analysis of Spring Supports in a Nuclear Fuel Spacer Grid

PDF

Topics: Boundary-value problems , Finite element analysis , Nuclear fuels , Springs

Research Studies in Support of Nuclear Power Plant Life Management

Michel R. Bie´th, Paolo Contri

ICONE 2008; 737-743https://doi.org/10.1115/ICONE16-48963

Abstract

View Articletitled, Research Studies in Support of Nuclear Power Plant Life Management

PDF

Topics: Nuclear power stations , Safety , Decision making , Knowledge management , Maintenance , Optimization , Plant design , Plant personnel

Advanced Applications of Nuclear Technology

A Novel Radiation Dosimetry Based on Optically Stimulated Luminescence

Yanping Liu, Zhaoyang Chen, Yanwei Fan, Weizhen Ba, Shilie Pan

ICONE 2008; 745-749https://doi.org/10.1115/ICONE16-48023

Abstract

View Articletitled, A Novel Radiation Dosimetry Based on Optically Stimulated Luminescence

PDF

Topics: Dosimetry , Luminescence , Radiation (Physics) , Dosimeters , Optical fiber , Airbags , Damage , Electromagnetic interference , Electronics , Energy consumption

Simulation of an X-RAY Fluorescence Experiment for Gold Assaying With Photon Interaction Probability and Moments Model

Zafar U. Koreshi, Sadaf Siddiq, Irfan A. Khan, Tasneem Shah

ICONE 2008; 751-757https://doi.org/10.1115/ICONE16-48026

Abstract

View Articletitled, Simulation of an X-RAY Fluorescence Experiment for Gold Assaying With Photon Interaction Probability and Moments Model

PDF

Topics: Assaying , Fluorescence , Photons , Probability , Simulation , X-rays , Disks , Shells , Absorption , Compton effect

On Advanced Fuel With Improved Properties

Alexander S. Kolokol, Alexander L. Shimkevich

ICONE 2008; 759-763https://doi.org/10.1115/ICONE16-48090

Abstract

View Articletitled, On Advanced Fuel With Improved Properties

PDF

Topics: Fuels , Mechanical admittance , Phonons , Thermal conductivity

Liquid Metal Lithium Jet Experiment for IFMIF Target

Takuji Kanemura, Hiroo Kondo, Nobuo Yamaoka, Seiji Miyamoto, Mizuho Ida, Hiroo Nakamura, Izuru Matsushita, Takeo Muroga, Hiroshi Horiike

ICONE 2008; 765-774https://doi.org/10.1115/ICONE16-48171

Abstract

View Articletitled, Liquid Metal Lithium Jet Experiment for IFMIF Target

PDF

Topics: Liquid metals , Lithium , Wakes

Tension Metastable Fluid Nuclear Particle Detector: Qualification and Comparisons

J. Lapinskas, P. Smagacz, Y. Xu, R. P. Taleyarkhan

ICONE 2008; 775-784https://doi.org/10.1115/ICONE16-48185

Abstract

View Articletitled, Tension Metastable Fluid Nuclear Particle Detector: Qualification and Comparisons

PDF

Topics: Fluids , Particulate matter , Sensors , Tension , Neutrons , Nuclear fission , Emissions , Instrumentation , Pressure , Temperature

Oil Recovery From Shale With Nuclear Generated Heat

Gary M. Sandquist, Jay F. Kunze, Vern C. Rogers

ICONE 2008; 785-789https://doi.org/10.1115/ICONE16-48188

Abstract

View Articletitled, Oil Recovery From Shale With Nuclear Generated Heat

PDF

Topics: Heat , Heating , Nuclear reactors , Petroleum extraction , Shales , Steam

Reliability and Safety Assessment of a Conceptual Thermochemical Plant for Nuclear-Based Hydrogen Generation

Yuepeng Zhang, Lixuan Lu, Greg F. Naterer

ICONE 2008; 791-797https://doi.org/10.1115/ICONE16-48265

Abstract

View Articletitled, Reliability and Safety Assessment of a Conceptual Thermochemical Plant for Nuclear-Based Hydrogen Generation

PDF

Topics: Hydrogen , Reliability , Safety , Nuclear power , Emissions , Heat , Risk , Accidents , Carbon dioxide , Cycles

The Technical Development for Reuse of Radioactive Concrete Waste Generated by Dismantling of Nuclear Facilities

Byung Youn Min, Wang Kyu Choi, Jung Woo Park, Chong Hun Jung, Won Zin Oh

ICONE 2008; 799-803https://doi.org/10.1115/ICONE16-48315

Abstract

View Articletitled, The Technical Development for Reuse of Radioactive Concrete Waste Generated by Dismantling of Nuclear Facilities

PDF

Topics: Concretes , Nuclear power stations , Heating , Temperature , Gravel , Sands , Separation (Technology) , Milling , Nuclides , Recycling

Transient Analysis of UO2 and MOX-Fueled Cores Based on Microscopic Reactor Physics

Toshikazu Takeda, Hiroaki Tagawa, Tadafumi Sano

ICONE 2008; 805-812https://doi.org/10.1115/ICONE16-48344

Abstract

View Articletitled, Transient Analysis of UO2 and MOX-Fueled Cores Based on Microscopic Reactor Physics

PDF

Topics: Physics , Transient analysis , Temperature , Fuels , Cross section (Physics) , Fuel rods , Light water reactors

Physics Principles to Achieve Comparable Fission Power From Fertile and Fissile Rods of the Conceptual ATBR/FTBR Reactors

Usha Pal, V. Jagannathan

ICONE 2008; 813-818https://doi.org/10.1115/ICONE16-48381

Abstract

View Articletitled, Physics Principles to Achieve Comparable Fission Power From Fertile and Fissile Rods of the Conceptual ATBR/FTBR Reactors

PDF

Topics: Nuclear fission , Physics , Rods

Hybrid Methods Approach for Solving Problems in Transport Theory

Rube´n Panta Pazos

ICONE 2008; 819-825https://doi.org/10.1115/ICONE16-48400

Abstract

View Articletitled, Hybrid Methods Approach for Solving Problems in Transport Theory

PDF

Topics: Transport theory , Numerical analysis , Resolution (Optics) , Algebra , Boundary-value problems , Collisions (Physics) , Computers , Design , Electromagnetic scattering , Geometry

Laser Joining of Ceramics: A Contribution to High Temperature Range Application of Ceramic Components

Wolfgang Lippmann, Marion Herrmann, Carmen Hille, Antonio Hurtado

ICONE 2008; 827-834https://doi.org/10.1115/ICONE16-48409

Abstract

View Articletitled, Laser Joining of Ceramics: A Contribution to High Temperature Range Application of Ceramic Components

PDF

Topics: Ceramics , High temperature , Industrial ceramics , Joining , Lasers , Oxide ceramics , Laser beams , Sensors , Brazing , Composite materials

Finding the Minimun of the Quadratic Functional in Variational Approach in Transport Theory Problems

Rube´n Panta Pazos

ICONE 2008; 835-840https://doi.org/10.1115/ICONE16-48479

Abstract

View Articletitled, Finding the Minimun of the Quadratic Functional in Variational Approach in Transport Theory Problems

PDF

Topics: Transport theory , Algorithms , Algebra , Collisions (Physics) , Computers , Construction , Electromagnetic scattering , Radiation scattering , Scattering (Physics)

Design Study of a Pilot Test Plant for Hydrogen Production by a Hybrid Thermochemical Process

Patrick Rivalier, Sophie Charton, Denis Ode, Jean Duhamet, Laurence Boisset, Jean-Louis Pabion, Florent Gandi, Jean-Pierre Croze

ICONE 2008; 841-849https://doi.org/10.1115/ICONE16-48584

Abstract

View Articletitled, Design Study of a Pilot Test Plant for Hydrogen Production by a Hybrid Thermochemical Process

PDF

Topics: Design , Hydrogen production , Cycles , Hydrogen , Electrolysis , Sulfur , Anodes , Fuel cells , High temperature , Industrial capacity

IAEA CRP Benchmark of Kalinin VVER-1000 NPP: An Analysis Using EXCEL-TRIHEX-FA Code System

Suhail Ahmad Khan, V. Jagannathan, R. P. Jain

ICONE 2008; 851-856https://doi.org/10.1115/ICONE16-48613

Abstract

View Articletitled, IAEA CRP Benchmark of Kalinin VVER-1000 NPP: An Analysis Using EXCEL-TRIHEX-FA Code System

PDF

Topics: Carbon reinforced plastics , Nuclear power stations , Diffusion (Physics) , Boron , Construction , Coolants , Density , Feedback , Finite difference methods , Manufacturing

Development of Remote Measuring System for RVI Modularization

Tae-Soon Kim, Jae-Gon Lee, Je-Jun Lee, Myeong-Man Park

ICONE 2008; 857-864https://doi.org/10.1115/ICONE16-48657

Abstract

View Articletitled, Development of Remote Measuring System for RVI Modularization

PDF

Topics: Calibration , Computers , Construction , Electricity (Physics) , Electromagnetic interference , Jigs and fixtures , Nuclear power stations , Nuclear reactors , Optimization , Probes

A Comparison of Fast Thorium Breeder Reactor Designs With Oxide and Metallic Fuels

V. Jagannathan, Usha Pal, R. Karthikeyan, Devesh Raj

ICONE 2008; 865-881https://doi.org/10.1115/ICONE16-48679

Abstract

View Articletitled, A Comparison of Fast Thorium Breeder Reactor Designs With Oxide and Metallic Fuels

PDF

Topics: Breeder reactors , Fuels , Coolants , Fuel rods , Fast neutron reactors , Flow (Dynamics) , Rods , Sodium , Uranium

Analyze and Simulation of a Typical MEMS RPG Using MCNP Code

sM. Mohamadian, S. A. H. Feghhi, H. Afarideh

ICONE 2008; 883-886https://doi.org/10.1115/ICONE16-48766

Abstract

View Articletitled, Analyze and Simulation of a Typical MEMS RPG Using MCNP Code

PDF

Topics: Microelectromechanical systems , Simulation , Generators , Radioisotopes , Atomic batteries , Beta particles , Electronics , Energy conversion , Kinetic energy , Piezoelectricity

Recent Advances in Nuclear-Based Hydrogen Production With the Thermochemical Copper-Chlorine Cycle

G. F. Naterer, K. Gabriel, Z. Wang

ICONE 2008; 887-893https://doi.org/10.1115/ICONE16-48791

Abstract

View Articletitled, Recent Advances in Nuclear-Based Hydrogen Production With the Thermochemical Copper-Chlorine Cycle

PDF

Topics: Copper , Cycles , Hydrogen production , Heat , Hydrogen , Methane , Oxygen , Steam , Sustainability , Water

Crosstalk and Time Response of a Plastic Scintillation Optical Fibers Array for Neutron Imaging

Yue-Lei Wu, Hua-Si Hu

ICONE 2008; 895-899https://doi.org/10.1115/ICONE16-48810

Abstract

View Articletitled, Crosstalk and Time Response of a Plastic Scintillation Optical Fibers Array for Neutron Imaging

PDF

Topics: Imaging , Neutrons , Optical fiber , Cladding systems (Building) , Engineering prototypes , Flight , Metal powders , Protons , Tungsten

Lattice Design of Dedicated Synchrotron for Proton Therapy

M. Hosseinzadeh, M. Ghergherechi, S. A. H. Feghhi, A. Mohammadzadeh, H. Afarideh

ICONE 2008; 901-905https://doi.org/10.1115/ICONE16-48832

Abstract

View Articletitled, Lattice Design of Dedicated Synchrotron for Proton Therapy

PDF

Topics: Design , Patient treatment , Protons , Cyclotrons , Proton beams , Cavities , Computers , Electrical measurement , Ions , Magnets

Gas Magnification of Multi-Gap Resistive Plate Chamber

Yue-Lei Wu, Hua-Si Hu, Yi-Chen Li

ICONE 2008; 907-912https://doi.org/10.1115/ICONE16-48839

Abstract

View Articletitled, Gas Magnification of Multi-Gap Resistive Plate Chamber

PDF

Topics: Magnification , Data acquisition systems , Instrumentation , Simulation , Vickers hardness testing

Codes, Standards, Licensing and Regulatory Issues

Risk Managed Technical Specification Implementation at South Texas Project Units 1 and 2

Ernie Kee, Drew Richards, C. Rick Grantom, James K. Liming

ICONE 2008; 913-920https://doi.org/10.1115/ICONE16-48150

Abstract

View Articletitled, Risk Managed Technical Specification Implementation at South Texas Project Units 1 and 2

PDF

Topics: Risk , Databases , Computer software , Pressurized water reactors

Regulatory Guide 1.200 PRA Peer Reviews: A Peer Reviewer Perspective

David J. Finnicum

ICONE 2008; 921-925https://doi.org/10.1115/ICONE16-48152

Abstract

View Articletitled, Regulatory Guide 1.200 PRA Peer Reviews: A Peer Reviewer Perspective

PDF

Topics: Boiling water reactors , Nuclear power stations , Pressurized water reactors , Probabilistic risk assessment , Resonance ionization spectroscopy , Risk , Teams

Generic Issues Program Overview and Update

Jack W. Foster, John V. Kauffman

ICONE 2008; 927-930https://doi.org/10.1115/ICONE16-48245

Abstract

View Articletitled, Generic Issues Program Overview and Update

PDF

Topics: Construction , Design , Nuclear decommissioning , Regulations , Safety , Uncertainty

Developing a Standard Code for Spent Fuel and High Level Waste Containment Baskets

Donald Wayne Lewis

ICONE 2008; 931-937https://doi.org/10.1115/ICONE16-48285

Abstract

View Articletitled, Developing a Standard Code for Spent Fuel and High Level Waste Containment Baskets

PDF

Topics: Containment , Spent nuclear fuels , Design , Storage , Transportation systems , Construction , Containment systems , Nuclear design , Radioactive substances , Shells

Review of Quality Assurance for CMRR at LANL

Taunia S. Wilde, Richard A. Holmes, Gary M. Sandquist

ICONE 2008; 939-946https://doi.org/10.1115/ICONE16-48322

Abstract

View Articletitled, Review of Quality Assurance for CMRR at LANL

PDF

Topics: Defense industry , Nuclear weapons , Quality control

Integration of Risk Insights Into Nuclear Power Plant Operations

Glen E. Schinzel

ICONE 2008; 947-956https://doi.org/10.1115/ICONE16-48444

Abstract

View Articletitled, Integration of Risk Insights Into Nuclear Power Plant Operations

PDF

Topics: Nuclear power plant operations , Risk , Surveillance , Nuclear power stations , Safety , Design , Feedback , Nuclear construction , Nuclear power , Nuclear reactors

Codes, Standards and Regulatory Topics for Nuclear Facilities

Taunia Wilde, Shannan Baker, Gary M. Sandquist

ICONE 2008; 957-961https://doi.org/10.1115/ICONE16-48476

Abstract

View Articletitled, Codes, Standards and Regulatory Topics for Nuclear Facilities

PDF

Topics: Nuclear power stations , Quality control , US Department of Defense , Construction , Decontamination , Design , Maintenance , Nuclear decommissioning

Development of Code Case N-755: Use of Polyethylene (PE) Plastic Pipe for Section III, Division 1, Construction and Section XI Repair/Replacement Activities

Frank J. Schaaf, Jr.

ICONE 2008; 963-969https://doi.org/10.1115/ICONE16-48495

Abstract

View Articletitled, Development of Code Case N-755: Use of Polyethylene (PE) Plastic Pipe for Section III, Division 1, Construction and Section XI Repair/Replacement Activities

PDF

Topics: Construction , Maintenance , Plastic pipes , Polyethylene pipes , Safety , Pipes , ASME Boiler and Pressure Vessel Code , Nuclear power stations , Testing , ASME Standards

Efforts Toward Risk Informed Regulation and Immediate Issues in Japan

Akihide Hidaka

ICONE 2008; 971-979https://doi.org/10.1115/ICONE16-48569

Abstract

View Articletitled, Efforts Toward Risk Informed Regulation and Immediate Issues in Japan

PDF

Topics: Risk , Risk communication , Risk-based decision making , Risk-based regulations , Safety

Scratch Tip Radius Effects on K-Controlled Slow Crack Growth in PE Pipe

Carlos R. Corleto, Brian B. Cole

ICONE 2008; 981-985https://doi.org/10.1115/ICONE16-48577

Abstract

View Articletitled, Scratch Tip Radius Effects on <em>K</em>-Controlled Slow Crack Growth in PE Pipe

PDF

Topics: Fracture (Materials) , Polyethylene pipes , Pipes , Finite element analysis , Hoop stress , Stress , ASTM International , Failure , High temperature , Pipe and tube industry

Selecting HLR and SR Standards for PRA Applications

Steven E. Farkas

ICONE 2008; 987-994https://doi.org/10.1115/ICONE16-48598

Abstract

View Articletitled, Selecting HLR and SR Standards for PRA Applications

PDF

Topics: Airbags , ASME Standards , Nuclear power stations , Probabilistic risk assessment , Risk , Risk assessment

The Rulemaking Process and Its Effect on the Use of ASME Nuclear Codes and Standards in the USA

Mark J. Ferlisi, Raymond A. West, David R. Lewis

ICONE 2008; 995-998https://doi.org/10.1115/ICONE16-48721

Abstract

View Articletitled, The Rulemaking Process and Its Effect on the Use of ASME Nuclear Codes and Standards in the USA

PDF

Topics: Engineering standards , Nuclear engineering , Regulations

Development of an ASME Code for Graphite Core Components

Christian A. Sanna

ICONE 2008; 999-1004https://doi.org/10.1115/ICONE16-48728

Abstract

View Articletitled, Development of an ASME Code for Graphite Core Components

PDF

Topics: ASME Standards , Graphite , Nuclear power

Risk-Informed Safety Classification for New Plant Designs

Nathan A. Palm

ICONE 2008; 1005-1009https://doi.org/10.1115/ICONE16-48752

Abstract

View Articletitled, Risk-Informed Safety Classification for New Plant Designs

PDF

Topics: Plant design , Risk , Safety , ASME Boiler and Pressure Vessel Code , Power stations

Current Endorsement of Consensus Codes for Regulatory Technical Standards in Japan

Kenji Tada, Tadao Kanda, Takayuki Sakuma, Masataka Tanimoto, Kazuhide Kitahara, Mikio Kurihara, Yukinori Goto, Zenichi Ogiso

ICONE 2008; 1011-1018https://doi.org/10.1115/ICONE16-48829

Abstract

View Articletitled, Current Endorsement of Consensus Codes for Regulatory Technical Standards in Japan

PDF

Topics: Engineering standards

Use of Polyethylene (PE) Pipe in Safety-Related, Class 3, Service-Water Piping

Prabhat Krishnaswamy, Eric M. Focht, Do-Jun Shim, Tao Zhang

ICONE 2008; 1019-1023https://doi.org/10.1115/ICONE16-48830

Abstract

View Articletitled, Use of Polyethylene (PE) Pipe in Safety-Related, Class 3, Service-Water Piping

PDF

Topics: Pipes , Safety , Water , ASME Boiler and Pressure Vessel Code , Polyethylene pipes , Design , Fracture (Materials) , Pressure , Temperature , Construction

Theory to Practice: The Realities of New Reactor Licensing Application Docketing and Review

Randolph R. Mahan, Kathryn M. Sutton, Douglas J. Rosinski

ICONE 2008; 1025-1034https://doi.org/10.1115/ICONE16-48852

Abstract

View Articletitled, Theory to Practice: The Realities of New Reactor Licensing Application Docketing and Review

PDF

Topics: Licensing

The Health of Risk-Informed Regulation

Robert J. Lutz, Raymond Schneider

ICONE 2008; 1035-1043https://doi.org/10.1115/ICONE16-48898

Abstract

View Articletitled, The Health of Risk-Informed Regulation

PDF

Topics: Risk-based regulations , Risk , Regulations , Fire , Fire risk , In-service inspection , In-service testing , Pressurized water reactors , Probabilistic risk assessment , Quality control