12th International
Conference on
Structural Mechanics
in Reactor Technology
|
12th International
Conference on |
|
DIVISION C: FUEL, CORE STRUCTURES,
AND FUEL ELEMENT STORAGE
(The papers with links are those received
by the SMiRT 12 Secretariat at the time the Transactions went to press)
C01: Fuel Element Structure Analysis
| C01/1 |
Modeling Post-Leakage LWR Fuel Rod
Behavior Using FREY-01 |
| C01/2 | Modelization
of the Mechanical Behaviour of Fractured Nuclear Fuel Pellets Bernaudat, Ch. |
| C01/3 | A Spherically Symmetric
Model for the Mechanical Behavior of Irradiated Fuel Particles Pelessone, D. |
| C01/4 | A
Computer Code Pulsar Tutnov, Alexadar A., Tutnov, Anton A., Ulyanov, A.I. |
C02: Fuel Element Cladding (1)
| C02/1 |
Influence of Manufacturing
Process on the Inreactor Creep Anisotropy of Stress-Relieved Zircaloy-2
Cladding |
| C02/2 | Thermal
Creep Mechanisms in a Zr-1Nb-1Sn-0.2Fe Sheet Kim, Young Suk |
| C02/3 | Transitional
Creep-Mechanisms in a Zr-1Nb-1Sn-0.2Fe Sheet Murty, K.L., Ravi, J., Wiratmo |
| C02/4 | Deformation
Mechanisms and Anisotropy in Zircaloy-4 and Nb-Modified Zirconium Alloy
Sheets Using Load Relaxation Technique Webber, K., Murty, K.L. |
| C02/5 | Stress
Corrosion Cracking Damage Modelling of Zircaloy 4 Cladding Joseph, J., Abonneau, E., Schuster, I., Chaigne, G. |
C03: Fuel Element Cladding (2)
| C03/1 |
Rupture and
Fragmentation of Pressurised Pipes and Fast Reactor Fuel Pins |
| C03/2 | Influence
of Irradiation on Iodine-Induced Stress corrosion Cracking Behavior of Zircaloy
4 Schuster, I., Lemaignan, C., Joseph, J. |
| C03/3 | Out-Pile Corrosion Behavior
of Zircaloy 4 Fuel Claddings
Under a High PH Operation Han, J.H., Kim, Y.S., Rheem, K.S., Chung, Y.G., Song, M.J. |
| C03/4 | Development
of Computer Code for PHWR Fuel Element Analysis Swami Prasad, P., Dutta, B.K., Kushwaha, H.S., Kakodkar, A. |
| C03/5 | Investigation
and Modelling of Stress Corrosion Cracking (SCC) of Fuel Rod Cladding in
Iodine Environment Kiselevsky, V., Stukalov, A. |
C04: Pellet Cladding Interaction
| C04/1 |
Analysis
of Pellet-Cladding Mechanical Interaction Behaviour of Different ABB Atom
Fuel Rod Designs |
| C04/2 | Pellet
Clad Interaction in PWR Fuel: Analytical Irridation Experiments and Finite
Element Modelling Caillot, L., Linet, B., Lemaignan, C. |
| C04/3 | A
Model for Predicting Pellet-Cladding Interaction Induced Fuel Rod Failure,
Based on Nonlinear Fracture Mechanics Jernkvist, L.-O. |
| C04/4 | Influence
of Pellet Geometries on Sheat Stresses and Strains Prasad, P.N., Alex, B., Upendra, D.B. |
| C04/5 | Modeling
of Local Pellet-Cladding Interaction on Stainless Steel and Zircaloy Fuel
Rods Silva, A.T., Esteves, A.M. |
C05: Fuel Assembly
| C05/1 | Effect
of Fuel Assembly Mechanical Design Changes on Dynamic Response of Reactor
Pressure Vessel System Under Extreme Loadings Bhandari, D.R., Hankinson, M.F. |
| C05/2 | CASI:
Prediction of Fuel Assembly - Axial Behaviour Under Irradiation Salaun, H., Callens, C., De Perthuis, S., Leroux, J.C. |
| C05/3 | Nonlinear
Analyses of the Buckling Load and the Eigenvalues in a 17x17 PWR Fuel Assembly Helen, J., Johansson, A. |
| C05/4 | Lateral
Compression Strength of Graphite Fuel Element Ho, F.-H. |
C06: Fabrication, Irradiation and Operation Experience
| C06/1 | Calculation
of RCCA Wear Reject Criteria in Nuclear Plants Bernaudat, Ch., Christodoulou, K. |
| C06/2 | Testing
of FBR Fuel and Core Structural Materials in a Materials Testing Reactor Debarberis, L., Moss, R.L., Tsotridis, G. |
| C06/3 | Prototype
Fuel Fabrication in Mexico Nocetti, C.A. |
| C06/4 | Design and Irradiation
Experience With Thorium Based Fuels in PHWRS Das, M. |
| C06/5 | The
Effect of Process Parameters on Structural Integrity of Coated Target Particles
During Fabrication Ho, F.-H. |
C07: Core Structure
| C07/1 | Dynamic
Responses of the Core Barrel for Pipe Breaks Jhung, M.-J., Song, H.G., Park, K.B., Hwang, W.G. |
| C07/2 | Dynamic
Numerical Model and Experimental Analysis of the Atucha 1 PWR Alvarez, L.M., Mancini, G.R., Porto, J. |
| C07/3 | Analysis
of the Interaction Between Fuel Elements and Supporting Grid in Local Conditions De Noronha, R.F., De Oliveira, C.A. |
| C07/4 | Vibration
Testing and Analysis of Cylindrical Shell Under Various Symmetrical/Asymmetrical
End Conditions Kuzelka, V., Cigler, L. |
| C07/5 | Creep,
Growth and Sag Analysis of Coolant Channel Assembly of Pressurised Heavy
Water Reactors Sharma, A., Malshe, U.D., Sinha, R.K., Kakodkar, A. |
C08:
Specific Fuel Element Design Problems
| C08/1 | Development
of Irradiation-Induced Stress Analysis Code-System for Graphite Components
in Gas-Cooled Reactor Ishihara, M., Iyoku, T., Shiozawa, S., Shirai, H., Takikawa, N. |
| C08/2 | Stress
Analysis of ABB Atom's Modified Control Rod Blade Under Pressure Loads
Chmielewski, T. |
| C08/3 | Development
of a Computer Program for Drop Time and Impact Velocity of the Rod Cluster
Control Assembly Yim, J.-S., Kim, I.K., Choi, K.-S., Kim, K.-T. |
| C08/4 | Design of Moderator
Sparger Channel for Pressurised Heavy Water Reactors Sharma, A., Sinha, R.K., Kokodkar, A. |
| C08/5 | Design
and Development of Rolled Joint for Moderator Sparger Channel of an Indian
Pressurised Heavy Water Reactor Shina, R.K., Joemon, V. |
| C08/6 | Model for the Mechanical
Behavior of Irridated Fuel Particles Pelessone, D. |