7th International
Conference on
Structural Mechanics
in Reactor Technology
|
7th International
Conference on |
|
DIVISION C: STRUCTURAL ANALYSIS
OF FUEL,
CLADDING AND ASSEMBLIES
C1 - Material Properties and Behavior Models
| C1/1 |
Fracture Mechanics Analysis of Iodine-Induced Crack
Growth in Zircaloy-4 Tubing Between 500 and 700°C |
| C1/2 | In Pile Creep Behaviour of Zry-4 and ZrNb3Sn1
Cladding Under Uniaxial and Biaxial Stress G. Böhner, M. Gärtner, A. Reymann, B. Wildhagen, H. Wilhelm |
| C1/3 | Mechanical Properties of Irradiated
Fast Breeder Reactor Cladding and Ducts G.D. Johnson, C.W. Hunter |
| C1/4 | Fuel Transient Deformation O.D. Slagle, F.E. Bard, B.C. Gneiting, J.R. Thielges |
| C1/5 | Fission Gas Release During
the SPX-1-HCDA G.L. Fiorini, A. Languille |
| C1/7 | Some Phenomenological and Basic
Models in Fuel Rod Simulation S. Harriague, E.J. Savino, C.A. Baigorria |
C2 - Thermal Reactor Fuel Transient Analysis I
| C2/1 |
LOCA Rupture Strains and Coolability of Full-Length
PWR Fuel Bundles |
| C2/2 | Capabilities and Limitations of Fuel Rod Evaluation
System - FREY Y.R. Rashid, R.S. Dunham |
| C2/3 | Modelling of Azimuthal Effects
Arising from Interaction Between Clad Deformation and Heat Transfer Under
LB-LOCA Conditions H. Laval, F. Casadei, P.M. Jones |
| C2/4 | A Model for Asymmetric Ballooning
and Analyses of Ballooning Behaviour of Single Rods with Probabilistic Methods J.G. Keusenhoff, J.D. Schubert, A.K. Chakraborty |
| C2/5 | Axial Fuel Relocation in Ballooning
Fuel Rods L.J. Siefken |
C3 - Thermal Reactor Fuel Transient Analysis II
| C3/1 |
Description and Assessment of Deformation and Temperature
Models in the FRAP-T6 Code |
| C3/2 | Description of Advanced Deformation
Models for FRAP-6 V.N. Shah, E.R. Carlson, G.A. Berna |
| C3/3 | Comparison of the SCDAP Computer
Code with Bundle Data Under Severe Accident Conditions C.M. Allison, T.M. Howe, G.P. Marino |
| C3/5 | Fuel Thermal Behaviour Under
Transient Conditions C.A. Baigorria |
| C3/6 | SAFENR - A Two Dimensional
Axisymmetric Finite Element Code for Predicting Behaviour of PHWR Fuel A.G. Chhatre, M. Das, R.S. Rustagi |
C4 - Fast Reactor Fuel Transient Analysis
| C4/1 |
Coupling of Fuel-Pin and Thermohydraulic Modules in
Computer Programs for Reactor Core Analyses |
| C4/2 | The Clad Rupture in the CABRI-TOP
LMFBR Safety Experiments J.C. Melis, J.C. Barescut, J.M. Berniolles, M. Eddi, J.M. Frizonnet |
| C4/3 | Current Status of the Transient
Integral Fuel Element Performance Code URANUS T. Preusser, K. Lassmann |
| C4/4 | Application and Results of
the Transient Integral Fuel Element Performance Code URANUS to FBR Hypothetical
Accident Analysis T. Preusser, K. Lassmann |
| C4/5 | Comparison of LIFE and TEMECH Code Predictions
with Treat Transient Tests B.C. Gneiting, F.E. Bard, J.R. Thielges |
| C4/7 | Transient Pellet-Cladding Interaction
of LMFBR Fuel Rods - Computer Code ISUNE-5 B.M. Ma |
C5 - Fuel Elements Analysis and Performance Evaluation
| C5/1 |
Cladding Breaches in a Fast Reactor Mixed-Oxide Fuel
Assembly |
| C5/2 | High Burnup, High Power Irradiation
Behavior of Helium-Bonded Mixed Carbide Fuel Pins P.J. Levine, U.P. Nayak, A. Boltax |
| C5/3 | Finite Element Analysis of
Inner and Outer Contracts of LMFBR Fuel Elements E. Zolti |
| C5/4 | An Experimentally-Supported Method for the
Estimation of LMFBR Fuel Operational Reliability B.L. Harbourne, J.T. Tatsumi, K.H. Chen, J.D. Stephen |
| C5/5 | Deformation and Collapse of
Zircaloy Fuel Rod Cladding into Plenum Axial Gaps P.L. Pfenniwerth, D.A. Gorscak, I.A. Selsley |
| C5/6 | Pellet to Cladding Interaction
Modeling with the Finite Element Code TITUS J. Joseph, A.M. Lefebvre-Albaret, M. Fillatre, R. Schley |
| C5/8 | The CyGRO5 Fuel Rod Analysis
Computer Program J.B. Newman, S.E. Kovscek |
| C5/9 | The Behavior of HTR Fuel Under
Irradiation H.-J. Allelein, R. Bornschein, H. Nabielek, A. Christ, D.L. Hanson |
C6 - Thermal Reactor Fuel Assemblies and Core Components
| C6/1 |
CASAC: A Code Computing the LOCA and Seismic Loading
on PWR Fuel Assemblies |
| C6/2 | Structural Analysis of PWR
Fuel Assemblies in LOCA and Seismic Conditions J.C. Leroux, M. Monchanin, R. Mortgat |
| C6/3 | Analysis of the Loading of
the PWR Reactor Control Rod Elements in Operating Conditions J.C. Leroux, B. Grattier |
| C6/4 | Mesure de vibrations de crayon
d'élément Combustible sous éncoulement par vibrométrie
laser P. Bouchard, J.L. Rigot, J.E. Chait |
| C6/5 | Structural Analysis of Transversely Loaded
HTGR Fuel Columns R.S. Alloway |
| C6/6 | The Structural Integrity of Core Components
of an HTR-MODULE J.G. Willaschek |
| C6/7 | Impact Tests on Scale Models
of a Shock Absorber for a LWR Spent Fuel Transport Packaging D. Aquaro, G. Forasassi |
| C6/8 | Dynamic Responses of Fuel and
Target Assemblies of a Production Reactor D.A. Crowley, W.F. Yau |
C7 - Fast Reactor Fuel Assembly Analysis
| C7/1 |
Nonlinear, Inelastic Fast Reactor Subassembly Interaction Analyses |
| C7/2 | Mechanical Behavior of a Fast
Reactor Core. Application of the 3D Codes to SUPER PHENIX 1 A. Bernard, P. Masoni, J.P. Van Dorsselaere |
| C7/3 | Investigations of Local Blockage
Formation and Dependance on Fuel Element Spacing G.F. Schultheiss, Ch. v. Minden |
| C7/4 | XEBRA Evaluation of the Mechanical
and Thermal-Hydraulic Performance of Distorted Fuel Pin Bundles K.H. Chen, S. Kaplan, J.D. Stephens |
| C7/5 | ÉTOILE: A Three-Dimensional
Finite Element Code for Analyzing Fuel Pin Deformations in an LMFBR Assembly M. Nakagawa |