17th International
Conference on
Structural Mechanics
in Reactor Technology
|
17th International
Conference on |
|
DIVISION C: FUEL AND CORE STRUCTURES
C01 - Fuel Vibration and Fretting
| C01-1 |
Prediction of Flow Induced Damping of a PWR Fuel
Assembly in Case of Seismic and Loca Load Case (C083) |
| C01-2 | Validation of PWR Core
Seismic Models with Shaking Table Tests on Interacting Scale 1 Fuel Assemblies
(C431) E. Viallet, G. Bolsee , B. Ladouceur, T. Goubin, J. Rigaudeau |
| C01-3 | Vibration Analysis of
a Dummy Fuel Rod Continuously Supported by Spacer Grids (C089) Myoung-Hwan Choi, Heung-Seok Kang, Kyung-Ho Yoon, Kee-Nam Song, Youn-Ho Jung |
| C01-4 | Modal Testing and Identification
of a PWR Fuel Assembly (C188) Stéphane Pisapia, Bruno Collard, Sergio Bellizzi, Vincent Mori |
| C01-5 | Water Confinement Effects
on Fuel Assembly Motion and Damping (C238) B. Brenneman, S.J. Shah, G.T.Williams, J.H. Strumpell |
C02 - Fuel Design and Constitutive Modelling
| C02-1 |
A Sensitivity Study on the Fuel Rod Hydraulic
Instability for the Advanced 16X16 Fuel Development (C501) |
| C02-2 | Calculational Analysis
of WWER-1000 Fuel Assembly Operational Deformation (C179) V.L.Danilov, S.V.Zarubin, V.P.Semishkin, N.V.Shary |
| C02-3 | Large Grain Size UO2 Sintered
Pellets Obtaining used for Burn up Extension (C009) Dumitru Ohâi |
| C02-4 | Optimization of Procedures
for Manufacture of Tubular Claddings and Pressure Tubes (C318) Igor Matsegorin, Alexander Semenov, Eugeny Rivkin, Boris Rodchenkov |
| C02-5 | Performance of Mexican
Fuel at the Laguna Verde Nuclear Power Plant (C257) Carlos A. Nocetti, Raúl Perusquia, Octavio Ovilla |
| C02-6 | Modeling of the Cold Work
Stress Relieved Zircaloy-4 Cladding Tubes Mechanical Behavior under PWR
Operating Conditions Fabrice Richard, Patrick Delobelle, Sylvain Leclercq, Pol Bouffioux, Gilles Rousselier |
C03 - Fuel Failure under Operation and Accident Conditions
| C03-1 |
Modelling of Fuel Rod Hydriding Failures in Water
Reactors (C194) |
| C03-2 | Theoretical
and Experimental Modeling of the Multiple Pressure Tube Rapture for RBMK
Reactor. Part I (C228) Natalya Y. Medvedeva, Igor A. Peshkov, Andrey V. Andreev, Robert V. Goldstein, Yuri V. Zhitnikov, Ilya V. Kadochnikov |
| C03-3 | Scenario for the Damage
of PWR Fuel Cladding in Situations of Pellet-Cladding Interaction
(C288) Gilles Rousselier, Sylvain Leclercq, Olivier Diard |
| C03-4 | Prediction of Failure
of Highly Irradiated Zircaloy Clad Tubes under Reactivity Initiated Accidents
(C037) Lars O. Jernkvist |
| C03-5 | Analysis of Power History
Effect for Cladding Stress during Power Ramp by FEMAXI-IV (C269) Shuhei Takeda |
| C03-6 | Effect of External Hydride
Layer on Fuel-Cladding Deformation during EDC-Testing (C374) Y. Ménager , A. G. Varias |
C04 - Components and Material Behaviour under Irradiation
| C04-1 |
Advanced Spacer Grid Design for the PLUS7 Fuel
Assembly (C378) |
| C04-2 | Studies on the Stress-strain
State of Spacer Grids and Claddings (C317) Igor Matsegorin, Alexander Semenov, Denis Severinov, Eugeny Rivkin, Anatoliy Kupalov-Yaropolk |
| C04-3 | Mechanical Charasterictics
of the HANARO Fuel Capsule (C171) Y. H. Kang, Y. J. Kim, B. G. Kim, Y. S. Lee, H. S. Kim, Y. J. Choi |
| C04-4 | Presentation of a New
Methodology of Chained Computations using Instationary 3D Approaches for
the Determination of Thermal Fatigue in a T Junction of a PWR Nuclear Plant
(C492) Sofiane Benhamadouche, Marc Sakiz, Christophe Péniguel, Jean-Michel Stéphan |
| C04-5 | The Risk Impact of Aging/Degradation
of Barrel-Baffle Bolts on a PWR Plant (C503) Ching-Hui Wu, Tsu-Mu Kao, Tsu-Jen Lin |
| C04-6 | Deformation and Fracture
of Irradiated Stainless Steel (C389) H. Tsai, T. R. Allen, J. Cole, T. Yoshitake, I. Yamagata |
C05 - Integrity of Fuel Systems under Transient Conditions
| C05-1 |
High Temperature Mechanical Behavior of Zr-2,5
% Nb Alloy (C273) |
| C05-2 | Fatique Properties of
a Cast Iron for the Reactor Fuel Carrier Candidate Heavy Thickness Tube
(C087) Shigetomo Nunomura, Yasuhiro Yamasaki, Wu Shi Pink |
| C05-3 | Calculations of Fuel Rod
Cladding Deformation for a Reactor Plant Wwer-1000 Under LB Loca
(C180) Yu Dragunov, V.Semishkin, Eu. Frizen, N.Shary |
| C05-4 | Fuel Dimensional Stability
in Czech Wwer Reactors (C472) J. Belac, D.Ernst, M. Lehmann, V. Mecir, A. Miasnikov, R. Svoboda, S. Stech, P. Vesely, M. Valach |
| C05-5 | Severe Core Damage Experiments
and Analysis for CANDU Applications (C069) P.M. Mathew, A.J. White, V.G. Snell, M. Bonechi |