13th International Conference on 
Structural Mechanics in Reactor Technology


 

DIVISION C: FUEL AND CORE STRUCTURES,
CORE MELT AND SEVERE ACCIDENT CONDITIONS

 

C01 Development of CFD Method to Evaluate 3-D Flow Characteristics for PWR Fuel Assembly
Imaizumi, M., Ichioka, T., Hoshi, M., Teshima, H., Kobayashi, H., Yokoyama, T.
C02 Fuel Assembly Bow: Analytical Modeling and Resulting Design Improvements
Stabel, J., Hubsch, H-P.
C03 Mexican Experience in Nuclear Fuel Fabrication
Nocetti, C.A., Torres, J.R., Leon, E.
C04 Residual Stress Measurements by Hole Drilling Method
Mansur, T.R., Di Lorenzo, R.F.
C05 Computing Reactivity Initiated Accidents in PWRs
Latche, J.C., Lamare, F., Cranga, M.
C06 Analysis of Fuel Rod Behaviour Under LOCA Using the STAV-T Fuel Performance Code
Jernkvist, L.O., Limback, M.
C07 Simulation of Accident and Normal Fuel Rod Work with Zr-Cladding
Tutnov, Anton A., Tutnov, Alexander A.
C08 Lift-Off Characteristics of PWR Fuel Assemblies for Tributary Pipe Break and Earthquake
Jhung, M.J., Kim, T.H.
C09 Computing PWR Fuel Assemblies Behaviour Under Seismic Solicitations
Jacquart, G.
C010 Structural Analysis of PWR Fuel Assemblies
Macedo, L.V.S., Perrotta, J.A.
C011 Analysis of Stability and Stiffness of Spacer Grid
He, C., Li, P.
C012 Fuel Analysis Code 'Fair' and Its High Burnup Modelling Capabilities
Prasad, P.S., Dutta, B.K., Kushwaha, H.S., Mahajan, S.C., Kakodkar, A.
C013 Effect of Operating Temperatures of Fuel & Clad on Burnup Capability of FBTR Mixed Carbide Fuel
Puthiyavinayagam, P., Govindarajan, S., Chetal, S.C.
C014 Simulation of Isothermal Fission Gas Release
Denis, A., Piotrkowski, R.
C015 Fuel Temperature and Fission Gas Release Modelling in RODEX3
Shann, S.H., Billaux, M.R., Van Swam, L.F.
C016 Prediction of the Lower Head Failure Under Severe Accident
Arutyunyan, R.V., Bolshov, L.A., Yamshchikov, N.V., Boldyrev, A.V., Strizhov, V.F.
C017 The PWR Lower Head Under Excessive Loading - Model Experiments and Theoretical Assessments
Dolensky, B., Krieg, R.
C018 Finite Element Analysis of Thermal Stresses of the Reactor Vessel in a Severe Light Water Reactor Accident
Borovkov, A.I., Granovsky, V.S., Kovtunova, S.V., Semenov, A.S.
C019 Core Melting in the First PHEBUS FP Experiment
Livolant, M., Holtbeckel, H.F., Adroguer, B., Reppetto, G., Lamond, C.
C020 SVECHA Candling Model for Melt Relocation Process
Palagin, A.V.
C021 Chemical Interaction Between Zircaloy-4 and Inconel 718
Hofmann, P., Markiewicz, M.
C022 Study of the Corium Crust Stability
Gatt, J.M.
C023 Code Package SVECHA: Modelling of Core Degradation Phenomena
Veshchunov, M.S., Palagin, A.V., Volchek, A.M., Yamshchikov, N.V., Boldyrev, A.V.
C024

Modeling Of Liquid Phase Formation Due to the Solid Zircaloy-4/ Solid Stainless Steel Interaction
San Martin, G.E., Piotrkowski, R., Moyano, E., Garcia, E.A.

C025 Numerical Modelization of the Corium/Substratum System
Gatt, J.M., Buffe, L., Marchand, O.
C026 Mechanical Behavior Simulation of Oxidized Fuel Cladding
Boldyrev, A.V., Yamshchikov, N. V.
C027 Prestressed Reactor Pressure Vessel with Built-In Core Catcher
Wedellsborg, B.W.
C028 Research in the Field of Severe Accidents Performed by the European Union as Cost Shared Projects
Balz, W.E., van Goethem, G.
C029 Large Scale Hydrogen-Air Combustion Experiments with Dynamic H2-Injection and Spark Ignition
Breitung, W., Dorofeev, S.B., Sidorov, V.P.
C030 Validation of GASFLOW for Analysis of Steam/Hydrogen Transport And Combustion Processes in Nuclear Reactor Containments
Royl, P., Muller, C., Travis, 1.R., Wilson, T.
C031 A Study on Hydrogen Burn Due to the Operation of Containment Spray System
Park, S.Y., Kim, D.H., Jin, Y., Park, C.K.


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