12th International
Conference on
Structural Mechanics
in Reactor Technology
|
12th International
Conference on |
|
DIVISION E: FAST REACTOR CORE
AND COOLANT
CIRCUIT STRUCTURES
(The papers with links are those received
by the SMiRT 12 Secretariat at the time the Transactions went to press)
E01: Design of LMFBR Components (1)
| E01/1 |
Structural Integrity
of Reactor System for Top Entry Type FBR |
| E01/2 | Structural
Integrity of
Heat Exchanger Components for Top Entry Loop Type FBR Satoh, K., Kubota, J., Kashiwakura, J., Maruyama, S. |
| E01/3 | Structural
Integrity of
Tube Bundle and Other SHells of Intermediate Heat Exchanger in Prototype
Fast Breeder Reactor with Flow Zoning on Secondary Sodium Side Srinvasan, R., Chetal, S.C., Rajakumar, A., Vaidyanathan, G., Bhoje, S.B. |
| E01/4 | Modelling
of Core-Catcher Devices Caroli, C., Durin, M. |
| E01/5 | Experimental
Tests and Numerical Calculations of Reinforced Concrete Slabs Subjected
to Rigid Missile Impact Corsi, F., Di Giamberardino, P., Bung, H., Lepareux, M., Matheron, Ph. |
E02: Design of LMFBR Components (2)
| E02/1 |
Operating Temperatures for
PFBR |
| E02/2 | Structural
Integrity of Primary
Piping System of Top Entry Type
FBR Maeda, O., Ueta, M., Kamishima, Y, Adachi, S. |
| E02/3 | Elastic
and Inelastic Analysis of PFBR-IHX Under Sodium-Water Reaction Pressure Chellapandi, P.M., Venkataramana, K., Chetal, S.C., Bhoje, S.B. |
| E02/4 | Monitoring
of Pipe Displacements in French LMFBR Superphenix Foucher, N., Debaene, J.P., Renault, Y., Mrs. Blin |
| E02/5 | Structural
Integrity Evaluation of Primary Pump Discharge Pipe for PFBR Chellapandi, P., Biswas, A., Selvaraj, T., Bhoje, S.B. |
| E02/6 | Serviceability
Estimation of Fast Reactor Equipment Fastener Metal Gorynin, V.I., Timofeev, B.T., Kondratjev |
E03: Design Rules and Damage Assessment (1)
| E03/1 |
Improvement
of Elevated Temperature Structural Design: Guide for DFBR in Japan |
| E03/2 | Leak
Before Break Procedure for Sodium Boundary Components Riou, B., Sperandio, M., Hooton, D.G., Rathjen, P. |
| E03/3 | Strain
Limits for Elevated Temperature Design: Significance, Necessity, Usefulness.
Proposal of Categorizing and Improvement of Design Codes Kastl, H. |
| E03/4 | The
Effect of Stiff Ends on Stress Index of Welding Elbow Kamishima, Y., Dosaki, K., Ueta, M. |
E04: Design Rules and Damage Assessment (2)
| E04/1 |
A Design Procedure Against Thermal
Striping Damage in Fast Breeder Reactors |
| E04/2 | Shakedown
Design Assessments of Elevated Temperature LMFBR Structures Buckthorpe, D.E., Sinclair, E.G. |
| E04/3 | A
Simplified Method for Shakedown Analysis Gatt, J.M., Cabrillat, M.T. |
| E04/4 | Incorporation
of Alternating Plasticity in the Shakedown Method Buckthorpe, D., White, P.S. |
| E04/5 | Shakedown
Method with Strain Based Damage Estimates White, P.S., Buckthrope, D. |
| E04/6 | Study
of the Plastic Collapse Limits of Shell Structures Kamishima, Y. |
E05: Design Rules
and Damage Assessment (3)
| E05/1 | Calculation
with Chaboche's Elastic-Viscoplastic Model: Status and Future Developments Riou, B., Faure, O., Turbat, A., Waeckel, N., Autrusson, B. |
| E05/2 | Assessment
of the Progressive Deformation on the Basis of an Elastic Analysis Gatt, J.M., Cabrillat, M.T., Taleb, L. |
| E05/3 | Evaluation
of Thermal Ratchetting on Axisymmetric Thin Shells at the Free Level of
Sodium: Experimental Results and Elastic Analysis Cabrillat, M.T., Gatt, J.M., Schoulguine, P., Skiara, A. |
| E05/4 | Evaluation
of Thermal Ratchetting on Axisymmetric Thin Shells at the Free Level of
Sodium - Inelastic Analysis Cabrillat, M.T., Gatt, J.M. |
| E05/5 | Ratcheting
Design Method for 9Cr 1 Mo Steel Autrusson, B., Widloecher, J.L., de Smet, M. |
E06: Design Rules and Damage Assessment (4)
| E06/1 | Numerical
Interpretation of Test Results of Large Scale Structural Test Under Long-Term
Creep Fatigue Loading Breitling, H., Lohse, U., Rathjen, P., Maile, K., Purper, H. |
| E06/2 | Comparison
of Different Damage Laws for Creep Fatigue Life Assessment Cabrillat, M.T., Oudelet, D., Poette, C. |
| E06/3 | Evaluation
of Weldment Strength-Reduction Factors for Fast Reactor Components Considering
Gage Length Effect Koto, H., Sakon, T., Otani, T., Takahashi, Y., Nitta, A. |
| E06/4 | Effect
of Compressive Stress on Crack Initiation and Propagation in Creep-Fatigue Autrusson, B., Lejeail, Y., Aguilar, J. |
E07: Accident Studies
| E07/1 | Dynamic
Structural Response of Reactor-Core Subassemblies (Hexcans) Due to Accident
Over-Pressurization Pfeiffer, P.A., Kulak, R.F. |
| E07/2 | Analysis
of an ICDA in a Fast Reactor with Multiphase and Multicomponent Behaviour
Law Lepareux, M., Bung, H., Combescure, A., Aguilar, J., Flobert, J.F. |
| E07/3 | Behaviour
of the EFR Primary Containment Structures Under Whole Core Accident Loading Avallet, C., Cariou, Y., Kenworthy, G., Klingert, B., Christodoulou, K. |
| E07/4 | FMFR
Whole Core Accient (WCA) - Valadiation of the Plexus Code by Comparison
with Mara Tests Cariou, Y., Sperandio, M., Lepareux, M., Christodoulou, M. |
| E07/5 | SWAAM-LT:
The Long-Term, Sodium/Water Reaction Analysis Method Computer Code Shin, Y.W., Chung, H.H., Wiedermann, A.H., Tanabe, H. |
| E07/6 | Fuel
Fragments Transport Due to Liquid Thermophore Convection After Accident
with Reactor Core Destruction Likhanskiim, V.V., Loboiko, A.I. |
E08: Buckling (1)
| E08/1 | Benchmark
Study on Dynamic Buckling of a Hemispherical Shell Hoell, H., Comescure, A., de Paulis, A. |
| E08/2 | Pseudo-Dynamic
Buckling Experiments of Thin Cylindrical Shells Under Biaxial Seismic Loads Nakagawa, M., Ishihama, K., Ikeuchi, H., Hagiwara, Y., Akiyama, H. |
| E08/3 | Effect of Coupled Thermo-Mechanical
Loading on Dynamic Stability of Cylindrical Shells Sengupta, S., Kapuria, S., Chander, S. |
| E08/4 | Behavior
of Very Thin Cylindrical Shells Under Moving Axial Gradients of Temperature Comescure, A. |
| E08/5 | Stress
and Buckling Analysis of Inner Vessel of a Fast Breeder Nuclear Reactor Paramasivam, V., Bagchi, A. |
E09: Buckling (2)
| E09/1 | The
Effects of Geometrical Imperfection on Buckling Strength of Cylindrical
Shells in Bending Murakami, T., Yoguchi, H., Hirayama, H., Nakamura, H., Matsuura, S. |
| E09/2 | The
Effect of Thermal Loads on Buckling Strength of Cylindrical Shells Kawamoto, Y., Kodama, T., Matsuura, S. |
| E09/3 | Buckling
Behaviour of PFBR Main Vessel and Its Thermal Baffles Under Seismic Loadings Damodaran, S.P., Ravi, R., Chellapandi, P., Bhoje, S.B. |
| E09/4 | An
Evaluation Method for Plastic Buckling of Circular Cylindrical Shells Under
Shear Forces Okada, J., Iwata, K., Tsukimori, K., Nagata, T. |
| E09/5 | Cyclic
Post-Buckling Tests for Low Cycle Fatigue Failure of Buckled Cylinders by
Shear and Bending Modes Ogiso, S., Sasaki, T., Ooka, Y., Nakamura, H., Akiyama, H. |
E10: Dynamics and Vibrations in LMFBR (1)
| E10/1 | A
Parametric Study of Fluidelastic Instability and Wear Damage in Fast Reactor
Steam Generators Avallet, C., De Langre, E. |
| E10/2 | Flow
Induced Vibration Analysis of IHX Tube Bundle in PFBR Srinivasan, R., Chellapandi, P., Chetal, S.C., Bhoje, S.B. |
| E10/3 | Fluid
Elastic Instability Analysis of 1/16th Experimental Model of PFBR Main Vessel
Cooling Circuit Jalaldeen, S., Ravi, R., Chellapandi, P., Bhoje, S.B. |
| E10/4 | Experimental
Study of Flow Induced Vibration of Thermal Baffles of PFBR Jason Premnath, S.M., Thirumalai, M., Prabhakar, R., Kale, R.D. |
| E10/5 | Study
on Vibration Analysis Method for Fluid-Structure Interaction of a Top-Entry
Loop Type FBR: Experiment and Analysis of the Thermal Baffle in the Reactor
Vessel Ishihama, K., Sekine, K., Kimura, S., Nakagawa, K., Yamamoto, K., Moriya, S. |
E11:
Dynamics and Vibrations in LMFBR (2)
| E11/1 | Experimental
and Analytical Studies on the Multi-Surface Sloshing Characteristics of
a Top Entry Loop Type FBR Kimura, K.,Mieda, T., Funada, T., Yammoto, K., Moriya, S., Hagiwara, Y., Takakuwa, M., Kodama, T., Koike, K. |
| E11/2 | Calculation of the Loads
Induced by Pressure Wave Flow in Nuclear Reactor Piping Systems Pedroso, L.J., Puppin Macedo, A., De Carvalho, M.A.M. |
| E11/3 | Analytical
Approach on Pressure Drop Sources and Wave Reflections in a Nuclear Reactor
Due to Transients Pedroso, L.J., De Carvalho, M.A.M., Puppin Macedo, A. |
| E11/4 | Study
of Vibration Analysis Methods for Fluid-Structure Interaction of LMFBR Structure
- Flow Hole Tests Katayama, H., Yamamoto, K., Funda, T., Eguchi, Y., Moriya, S., Fujimoto, S., Iijima, T. |
| E11/5 | Experimental and Analytical
Studies on Vibration of Fluid-Structure Interaction for Suspended Pipes
in Vessel Yamamoto, K., Satoh, K., Funada, T., Eguchi, Y., Moriya, S., Kodama, T. |
E12:
Structural Seismic Studies
| E12/1 | The
Effect of Seismic Motion Characteristics on the Inelastic Response Reduction
of Cylindrical Shell Structures Hagiwara, Y., Yamamoto, K., Akiyama, H. |
| E12/2 | Liquid
Storage Tanks Under Seismic Excitations Tang, Y., Azis Uras, R., Chang, Y.W. |
| E12/3 | Seismic
Analysis of PFBR In-Vessel Transfer Machines Selvaraj, T., Chellapandi, P., Sulekh, C., Bhoje, S.B. |
| E12/4 | Hydrodynamic
Response of Viscous Fluids Under Seismic Excitation Ma, D.C. |
E13: Core Studies
| E13/1 | Experimental
and Analytical Studies on Vertical Response of FBR Core Components During
Seismic Events Aida, Y., Niwa, H., Kawamura, Y., Kobayashi, T., Kurihara, C., Nakamura, H., Toyoda, Y., Hagiwara, Y. |
| E13/2 | Development
of SAFA, A Seismic Analysis Program for FBR Core Components Horiuchi, T., Nakagawa, M., Kasai, H. |
| E13/3 | An
Analytical Model for Studying Effects of Gas Release from a Failed Pin of
a Liquid Metal Reactor Shin, Y.W. |
| E13/4 | LMFBR
Core Flowering Response to an Impulse Load Brochard, D., Petret, J.C., Queval, J.C., Gibert, R.-J. |
| E13/5 | Core
Mechanics of Large Fast Breeder Reactors - Sensitivity of Reactivity Feedback Nakagawa, M., Endo, H., Kawashima, M. |
| E13/6 | An Assessment of the
Chardis 2 Experimental Programme and the Validation of the Cramp Core Mechanics
Code Duthie, J.C., Herrick, A.R., Slater, I.J. |