2007 International LWR Fuel Performance Meeting

September 30 - October 3, 2007  •  San Francisco, California  •  Grand Hyatt San Francisco
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Technical Program

2007 International LWR Fuel Performance Meeting Topical Areas

  

Authors and Organizers of LWR Fuel 2007, please note the following abbreviations which indicate the status/progress of the abstracts and papers:


Abs.r = Abstract received awaiting review.
Abs.a = Abstract approved.
Draft = Draft received - sent for review.
Revd. = Draft reviewed.
Final = Final paper received.
Cdrom = All materials received (electronic paper and copyright information...) at LWR Fuel 2007 office and final paper sent to CD Publication.

0.00: Unassigned Abstracts/Papers

1.00: Advances in Nuclear Fuel Design and Fabrication

2.00: LWR Fuel Performance and Operational Experience

3.00: Fuel Cycle, Spent Fuel Storage and Transportation

4.00: Transient Fuel Behavior and Fuel Performance Methodologies and Test Facilities
 

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0.00: Unassigned Abstracts/Papers

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1.00: Advances in Nuclear Fuel Design and Fabrication
Peter Urban, AREVA NP; P.O. Box 3220, ; Erlangen , 91050 Germany; Ph: 49 9131 1895673 FAX: 49 9131 1894799 E-mail: peter.urban@areva.com

1.01 Fuel Assembly Design and Cladding
Lars Hallstadius, Westinghouse Atom AB; , ; Vasteras, SE 72163 Sweden; Ph: 46-21-347610 FAX: 46-21-347580 E-mail: lars.hallstadius@se.westinghouse.com
John Schardt, GE Energy, Nuclear; , ; , USA; Ph: FAX: E-mail: john.schardt@ge.com
1071Cdrom AREVA Cr2O3-Doped Fuel Development for BWRs 1    
1010Cdrom Overview on the Thermal and Mechanical Properties of HANA Claddings 1   2  
1103Cdrom Safety and Economic of High Power Density PWR with Novel Annular Fuel    
1101Cdrom High Mechanical Performance of AREVA Upgraded Fuel Assemblies for PWR in USA 1.   1.  
1091Cdrom Upgraded Fuel Assemblies for BWRs 1    

1.02 Fuel Assembly Design and Cladding-Poster Session
1076Cdrom Bi-content Gadolinia as Burnable Absorber in PWR to Improve the Reactor Core Behaviour 1   3  
1078Cdrom Thermal Behaviour of Advanced UO2 Fuel at High Burnup    

1.03 Fuel Fabrication, Methods and Models
Peter Urban, AREVA NP; P.O. Box 3220, ; Erlangen , 91050 Germany; Ph: 49 9131 1895673 FAX: 49 9131 1894799 E-mail: peter.urban@areva.com
Zeses E. Karoutas, Westinghouse; Fuel Component Facility, 102 Addison Rd ; Windsor, CT 06095 USA; Ph: 860 731 1859 FAX: 860 731 1824 E-mail: Zeses.E.Karoutas@us.westinghouse.com
1093Cdrom Controlled Beta-quench Treatment of Fuel Channels 0   1  
1025Cdrom The Manufacture and Performance of Homogeneous-Microstructure SBR MOX Fuel 1   2  
1081Cdrom Design, Feasibility, and Testing of Instrumented Rod Bundle to Improve Heat Transfer Knowledge in PWR Fuel Assemblies 1   4  
1053Cdrom CFD Simulations of a Flow Mixing and Heat Transfer Enhancement in an Advanced LWR Nuclear Fuel Assembly 1   2  
1070Cdrom ARCADIAŽ - A New Generation of Coupled Neutronics / Core Thermal-Hydraulics Code System at AREVA NP 4    

1.04 Fuel Fabrication, Methods and Models-Poster Session
1100Cdrom 3D Hydraulic Lift Force Models for AREVA Fuel Assembly in EDF PWRs 1   2  
1030Cdrom Heat Transfer Coefficient Variations in Nuclear Fuel Rod Bundles 1   2  
1007Cdrom First Principles CANDU Fuel Model and Validation Experimentation 1   4  
1106Cdrom Experience and Outlook for Development of Vibropack Oxide Fuel Pins for Light Water Reactors 1    

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2.00: LWR Fuel Performance and Operational Experience
Dirk Blavius, AREVA NP; 3315 Old Forrest Road, ; LYNCHBURG, VA 24506 USA; Ph: 434-832-3485 FAX: 434-382-4898 E-mail: Dirk.Blavius@Areva.com

2.01 Operating Experience, Fuel Reliability: BWR Fuel Performance
James Malone, Exelon; 4300 Winfield Road, ; Warrenville, IL 60555 USA; Ph: 630-657-2199 FAX: 630-657-4331 E-mail: james.malone@exeloncorp.com
Jack Fuller, GNF; , ; , USA; Ph: FAX: E-mail:
1097Cdrom Dimensional Behavior of Fuel Channels - Recent Experience and Consequences 2    
1087Cdrom GNF2 Operating Experience 2    
1061Cdrom Channel Bow in Boiling Water Reactors - Hot Cell Examination Results and Correlation to Measured Bow 2    
1035Cdrom Westinghouse BWR Fuel Reliability – Recent Experience and Analyses 2    

2.02 Operating Experience, Fuel Reliability: PWR Fuel Performance
Scott Ferguson, WCNOC; PO Box 411 (M/S CC-NE), ; Burlington , KS 66839-0411 USA; Ph: 620-364-8831 FAX: 620-364-4154 E-mail: scfergu@WCNOC.com
1099Cdrom Modern Fuel Cladding in Demanding Operation - ZIRLO in Full Life High Lithium PWR Coolant 2    
1038Cdrom Performance of Alloy M5™ Cladding and Structure 2   1  
1021Cdrom In-reactor Verification of Advanced Nuclear Fuel, PLUS7TM, for KSNPs 2   1  

2.03 Fuel Failure Mechanism and Analysis
Nicolas Waeckel, EDF; 12-14 Ave Dutrievoz (SEPTEN), ; Villeurbanne Cedex, 69628 France; Ph: 33-47-282-7244 FAX: 33-47-282-7711 E-mail: nicolas.waeckel@edf.fr
1080Cdrom Studies of Hydrogen Assisted Failures Initiating at the Cladding Outer Surface of High Burnup Fuel Using a Modified Ring Tensile Technique 2   4  
1023Cdrom Experimental Study on the Influence of the Supporting Condition and Rod Motion on the Fuel Fretting Damage 2   4  
1004Cdrom A Model for Predicting Coolant Activity Behaviour for Fuel-Failure Monitoring Analysis 2   4  

2.04 High Burn-up Fuel
Carl E. Beyer, PNNL; 902 Battelle Boulevard, PO Box 999 ; Richland, WA 99352 USA; Ph: 509-372-4605 FAX: 509-372-6485 E-mail: carl.beyer@pnl.gov
Kari Ranta-Puska, TVO; , ; , Finland; Ph: 358-961805410 FAX: E-mail: kari.ranta-puska@tvo.fi
1102Cdrom Fuel Modelling at Extended Burnup: IAEA Coordinated Research Project FUMEX-II 4   2  
1049Cdrom Thermal Diffusivity of Homogeneous SBR MOX Fuel with a Burn-up of 35 MWd/kgHM 2   3  
1043Cdrom Final Assessment of MOX Fuel Performance Experiment with Japanese PWR Specification Fuel in the HBWR 2   1  
1029Cdrom Fission Gas Distribution and Behavior in the High Burn-up Structure 2   4  

2.05 Fuel Rods and Structural Components
Pierre Mollard, AREVA NP; 10 rue Juliette Récamier, ; Lyon Cedex 06, 69456 France; Ph: FAX: E-mail: pierre.mollard@areva.com
Yong Hwan Jeong, KAERI; Zr Team, Duckjin-dong Yuseong; Daejeon, 305-600 Korea; Ph: 82-42-868-2322 FAX: 82-42-862-0432 E-mail: yhjeong@kaeri.re.kr
1055Cdrom Development of Modified MDA (M-MDA), PWR Fuel Cladding Tube for High Duty Operation in Future 2   1  
1051Cdrom The Effects of Cladding Chemical Composition on Corrosion Behavior of High Burnup BWR Fuel (Corrosion Properties of Low Iron and Low Silicon Content Cladding) 2    
1032Cdrom Fracture of Hydrided Zircaloy-4 Sheet under Through-Thickness Crack Growth Conditions 2   1  
1014Cdrom In-Reactor Creep Behavior of Zircaloy-2 2    

2.06 Influence of Water Chemistry on Fuel
John Willse, Framatome ANP; 3315 Old Forest Rd., ; Lynchburg , VA 24506-0935 USA; Ph: (434) 832-3437 FAX: 434-832-2629 E-mail: john.willse@areva.com
Motoyasu Kinoshita, CRIEPI; 2-11-1 Iwado Kita, Komae-shi ; Tokyo , 201-8511 Japan; Ph: 81-3-3480-2111, 070-5578-1039 (mobile) FAX: 81-3-3480-2493 E-mail: moto@criepi.denken.or.jp
1112Cdrom Electrochemical Potential (ECP) of Clean Heated Fuel Cladding Material and Structural SS under BWR Operating Conditions 2.06    
1110Cdrom AREVA NP Fuel Condition Index for Boiling Water Reactors 2.06    
1011Cdrom Water Chemistry Influence on AOA Phase 3 of the Spanish Experiment at Studsvik 2   4  

2.07 Operating Experience, Fuel Reliability: BWR Fuel Performance-Poster Session
1077Cdrom Fuel Performance Experience, Analysis and Modeling: Deformations, Fission Gas Release and Pellet-Clad Interaction 2   2  
1059Cdrom XEDOR - Reduced Order Stress Model for Online Maneuvering of Boiling Water Reactors 2   4  
1036Cdrom Burn-up Increase and Power Up-rate – Operation History of KKL 2   2  

2.08 Operating Experience, Fuel Reliability: PWR Fuel Performance-Poster Session
1088Cdrom Irradiation Test of Advanced PWR Fuel in Fuel Test Loop at HANARO 2   1  
1068Cdrom CHF Performance of Hybrid Mixing Vane Grid for Nuclear Fuel Bundle 2    

2.09 Fuel Failure Mechanism and Analysis-Poster Session
1113Cdrom ORNL Capability to Conduct Post Irradiation Examination of Full-Length Commercial Nuclear Fuel Rods 3    
1067Cdrom WWER Expert System for Fuel Failure Analysis Using Data on Primary Coolant Activity 2   4  
1033Cdrom The Necessity of a New Type Test Rig for the Development of an Evaluation Method in Grid Fretting Problems 2   1  
1024Cdrom Progress in the Research Programs to Elucidate Axial Cracking Fuel Failure at High Burnup 2   4  

2.10 High Burn-up Fuel-Poster Session
1001Cdrom Fuel Safety Activities in Korea 2    
1109Abs.a Study of Irradiation Induced Restructuring of High Burnup Fuel- (2) Use of Computer and Accelerator for Fuel Science and Development 4    
1064Cdrom Early Fission-gas Behavior in Oxide Fuel: Escape vs Trapping 2   1  
1054Cdrom The Width of High Burnup Structure in LWR UO2 Fuel 2   4  
1047Cdrom Irradiation Behaviour of the Large Grained UO2 Fuel Pellet in the Transient Conditions 2   4  
1031Cdrom A New Fission Gas Release Model for Predicting Gas Release during Steady State and Slow Power Ramps and for Initializing Fast Transients 2   4  
1026Cdrom Clarification of Rim Structure Effects on Properties and Behaviour of LWR UO2 Fuels and Gadolinia Doped Fuels 2    
1003Cdrom Estimation of the Influence of Plutonium Agglomerates in MOX Fuel on the Pellet Temperature 2   4  

2.11 Fuel Rods and Structural Components-Poster Session
1082Cdrom Investigation of Increased Hydriding of Guide Tubes in Ringhals 2 During Cycle Start-up 2   4  
1015Cdrom Corrosion and Hydrogen Pick-up Behaviors of Cladding and Structural Components in BWR High Burnup 9X9 Lead Use Assemblies 2   1  

2.12 Influence of Water Chemistry on Fuel-Poster Session
1111Cdrom Integrated Electronic Microscopy Method to Characterize BWR Crud Deposits 2.06    
1050Cdrom Phase Identifications in Crud from Commercial Boiling Water Reactors at the Idaho National Laboratory by Transmission Electron Microscopy 2   3  

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3.00: Fuel Cycle, Spent Fuel Storage and Transportation
James Tulenko, Univ of Florida; 202 NSC, PO Box 118300 ; Gainesville, FL 32611-8300 USA; Ph: 352-392-1401 x314 FAX: 352-392-3380 E-mail: tulenko@ufl.edu

3.01 Fuel Cycle, Spent Fuel Storage and Transportation
Robert Freeman, AREVA NP; , ; , USA; Ph: FAX: E-mail: Robert.Freeman@Areva.com
1084Cdrom Evaluation of Hoop Creep Behaviors in Long-term Dry Storage Condition of Pre-hydrided and High Burn-up Nuclear Fuel Cladding 3   4  
1083Cdrom Fabrication Characteristics of Large Grain DUPIC Pellet Using SIMFUEL 3   2  
1039Cdrom Threat of Hydride Re-orientation to Spent Fuel Integrity During Transportation Accidents: Myth or Reality? 3    
1016Cdrom Study on Hydride Reorientation in Zry-2 Fuel Claddings during Interim Dry Storage 3   2  

3.02 Fuel Cycle, Spent Fuel Storage and Transportation-Poster Session
1104Cdrom Requirements of Cask-Storage and Cask-Transport Licensing According to IAEA 1996 Rules for On-Site Storage of Spent Fuel in Germany – From the Utility’s Point of View 3    
1072Cdrom AREVA NP Next Generation Fresh UO2 Fuel Assembly Shipping Cask: SCALE - CRISTAL Comparisons Lead to Safety Criticality Confidence 3    
1058Cdrom Trans-Atlantic Fuel Fabrication: Security of Supply Program 3   1  

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4.00: Transient Fuel Behavior and Fuel Performance Methodologies and Test Facilities
Toyoshi Fuketa, JAEA; , ; , Japan; Ph: FAX: E-mail: fuketa.toyoshi@jaea.go.jp

4.01 Fuel Behavior during Design Basis Accidents (RIA and LOCA)
Javier Riverola, ENUSA; Santiago Rusinol 12, ; 28040 Madrid , Spain; Ph: 34913474228 FAX: 34913474421 E-mail: jrg@enusa.es
Samim Anghaie, Univ of Florida; 207 NSC, PO Box 118300 ; Gainesville, FL 32611-8300 USA; Ph: 352-392-8653 FAX: 352-392-8656 E-mail: anghaie@ufl.edu
1074Cdrom Overview of the M5™ Alloy Behavior under RIA and LOCA Conditions 4   2  
1052Cdrom JAEA Studies on High Burnup Fuel Behaviors during Reactivity-Initiated Accident and Loss-of-Coolant Accident 4    
1019Cdrom High Temperature Expansion Due to Compression Test for the Determination of a Cladding Material Failure Criterion under RIA Loading Conditions 4    
1018Cdrom Behavior of Zr1%Nb Fuel Cladding under Accident Conditions 4   2  
1108Cdrom The U. S. Nuclear Regulatory Commission’s Strategy for Revising the RIA Acceptance Criteria    

4.02 Fuel Behavior during Off-normal Transient
Peter Urban, AREVA NP; P.O. Box 3220, ; Erlangen , 91050 Germany; Ph: 49 9131 1895673 FAX: 49 9131 1894799 E-mail: peter.urban@areva.com
Jinzhao Zhang, Tractebel Engineering; Avenue Ariane 7, Bte 1 , B-1200 ; Brussels , Belgium; Ph: 32.2.773.9843 FAX: 32.2.773.8900 E-mail: jinzhao.zhang@tractebel.com
1069Cdrom ATWS Analysis with an Advanced Boiling Curve Approach within COBRA 3-CP 4    
1044Cdrom Multidimensional Modeling of a Ramp Test with the PWR Fuel Performance Code ALCYONE 4    
1022Cdrom The Mechanical Behavior of Pellet-Cladding with the Missing Chip under PCMI Loadings during Power Ramp 4   2  
1012Cdrom Computer Simulation of Non-congruent Melting of Non-stoichiometric Uranium Dioxide Fuel 4   2  

4.03 Neutronics, Thermal, Mechanical Methodologies
Nadine Hollasky, AVN; , ; , Belgium; Ph: FAX: E-mail: nh@avn.be
Toyoshi Fuketa, JAEA; , ; , Japan; Ph: FAX: E-mail: fuketa.toyoshi@jaea.go.jp
1075Cdrom The COPERNIC3 Project: How AREVA is Successfully Developing an Advanced Global Fuel Rod Performance Code 4   2  
1095Cdrom Impact of Plant Noise on BWR Stability Analyses 4   2  
1073Cdrom Approach to Analyze Potentially Limiting Hot Low Power BWR Control Rod Drop Accident 4    
1006Cdrom Non-Linear Dynamics Analysis of a PWR with up-to-date Fuel Design 4   1  

4.04 Fuel Behavior during Design Basis Accidents (RIA and LOCA)-Poster Session
1105Cdrom Multi-pin Studies of the Effect of Changes in PWR Fuel Design on Clad Ballooning and Flow Blockage in a Large-break Loss-of Coolant Accident 4.01   4.00  
1085Cdrom A Model for Assessment of Failure of LWR Fuel during an RIA 4    
1046Cdrom FRAPTRAN Predictability of High Burnup Advanced Fuel Performance: Analysis of the CABRI CIP0-1 and CIP0-2 Experiments 4   2  

4.05 Neutronics, Thermal, Mechanical Methodologies-Poster Session
1089Cdrom HIDUTYDRV Code, A Fuel Product Margin Tool 4   2  
1079Cdrom A 3D Behavior Modeling for Design and Performance Analysis of LWR Fuels 4   1  
1090Cdrom Prediction of Regions of Reduced Heat Transfer Downstream of Nuclear Fuel Spacer Grids 4   1  
1062Cdrom High Burnup Fuel Behavior Modeling and Licensing 4    
1057Cdrom Helium Production and Behavior in Nuclear Oxide Fuels during Irradiation in LWR 4    
1045Cdrom Direct Experimental Evaluation of the Grain Boundaries Gas Content in PWR Fuels : New Insight and Perspective of the ADAGIO Technique 4   2  

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The last update is: Tue Aug 21 09:28:35 2007