| 18th
International Conference on |
|
DIVISION C: FUEL AND CORE STRUCTURES
Fuel
Rod Vibration and Fretting
| C01-1 | New
Knowledge and Experiences of Flow Induced Fretting in PWR Fuel Assemblies Juergen Stabel, Mingmin Ren, Bruno Ladouceur |
| C01-3 | Vibration
Control of Nuclear Reactor Core Ruojing Zhang |
| C01-6 | Experimental
Study of Flow Induced Vibration of the Planar Fuel Assembly Jinhua Wang, Hanliang Bo, Shengyao Jiang, Haijun Jia, Wenxiang Zheng |
| C01-7 | Fuel
Rod to Support Contact Optimization for the 16x16 Next Generation Fuel Leo Alves Carrilho |
Fuel Assembly
Modeling
| C02-1 | The
PROMETRA Program: A Reliable Material Database for Highly Irradiated Zircaloy-4,
ZIRLO(TM) and M5(TM) Fuel Claddings Bernard Cazalis, Jean Desquines, Christian Bernaudat, Pascal Yvon, Christophe Poussard, Xavier Averty |
| C02-2 | Thermomechanical
Behavior of Mexican Fabricated Fuel Héctor Hernández López, Carlos A. Nocetti |
| C02-3 | Modeling
Contacts among Multiple CANDU Fuel Elements in a Bundle Shouze Xu, Shudong Yu, Mukesh Tayal, Zhen Xu |
| C02-4 | Improved
Fuel Assembly Dynamic Model Sudhir J. Shah, Ben Brenneman, John H. Strumpell, Gary T. Williams |
| C02-5 | Three-Dimensional
Modeling of CANDU Nuclear Fuel Elements in Bowing Analysis Shudong Yu |
| C02-6 | Analytical-and-Experimental
Simulation of WWER-1000 Fuel Rod Behaviour under Initial Stage of LB LOCA at the
Test Bench "Parameter" V.P. Semishkin, V.I. Nalivayev, V.S. Konstantinov, N.Ya. Parshin |
Clad
Integrity
| C03-1 | The
Fracture and Spallation of Zirconia Layers in High Burnup PWR Fuel Claddings Submitted
to RIA Transients Jean Desquines, V. Georgenthum, F. Lemoine, B. Cazalis |
| C03-2 | Development
of Welded Joints for Steel and Zirconium Tubes at Nuclear Power Plants Alexander Semenov, Vladimir Aden, Evgeny Rivkin, German Shevelyov, Vasiliy Tyurin |
| C03-3 | Analysis
of Pellet-Clad Interaction of LWR Fuel Rods during Power Ramps Ali R. Massih, Lars O. Jernkvist, Jan-Erik Lindbäck, Gang Zhou |
| C03-4 | Pellet
Cladding Mechanical Interaction Assessment Using 3D Modelling B. Michel, D. Plangcq, C. Struzik, Ph. Garcia, S. Lansiart |
| C03-5 | Influence
of Azimuth and Radial Neutron and Thermal Sources Anisotropy on Contact Problem
Simulation in Real Fuel Pellet-Cladding Configuration Using FEM Josef Belác, Mojmír Valach, Jirí Zymák |
Fuel
Assembly Dynamics
| C04-1 | Fracture
Toughness of Irradiated Zr-2.5Nb CANDU Pressure Tube Using Load Ratio Method Seung-Jin Oh, In-Sup Kim, Young-Suk Kim, Sang-Bok Ahn |
| C04-3 | Applying
the TRANSURANUS Code to VVER Fuel under Accident Conditions Csaba Gyori, Zoltán Hózer, Erzsébet Perez-Feró, Paul Van Uffelen, Arndt Schubert, Jacques van de Laar |
| C04-6 | Experimental
Investigation of Strain, Damage and Failure of Hydrided Zircaloy-4 with Various
Hydride Orientations Aude Racine, Michel Bornert, Daniel Caldemaison, Claude Sainte Catherine, Chantal Cappelaere |
| C04-7 | The
Stress Analysis and Stress Evaluates of y-Spectrometer-Probe Station Hailong Li |
Design of Advanced Reactor
Fuel
| C05-1 | Identification
of the Key Parameters Defining the Life of Graphite Core Components Mark N. Mitchell |
| C05-2 | Theoretical
and Experimental Modeling of the Multiple Pressure Tube Rupture for RBMK Reactor.
Part II Natalya Y. Medvedeva, Andrey V. Andreev, Sergey V. Timkin, Igor A. Peshkov, Vladislav N. Zhilko, Dimitri Ye. Martsiniouk, Olga A. Poshtovaya |
| C05-3 | Experimental
Study of New Generation WWER-1000 Fuel Assemblies at JSC NCCP Anatoly A. Enin, Vladimir V. Rozhkov, Mstislav A. Shustov, Alexander P. Ustimenko |
| C05-4 | Characterization
of Coated Nuclear Fuels by Nano-Indentation Yong Choi, Bong-Goo Kim, Y.W. Lee, J.K. Lee |
| C05-6 | MP98,
an Innovative Reactivity Control System for LWR and VHTR, Tests Results on Prototypes Michel Emin, Jean Francois Gagne |
Life
Assessment of Core Structure I
| C06-1 | Stress
Analysis of Two-Dimensional C/C Composite Components for HTGR'S Core Restraint
Mechanism Satoshi Hanawa, Junya Sumita, Taiju Shibata, Masahiro Ishihara, Tatsuo Iyoku, Kazuhiro Sawa |
| C06-2 | Towards
a Better Understanding of the Role of Stress in Restructuring of Radiation Damage Jérome Jonnet, Paul Van Uffelen, Dragos Staicu, Thierery Wiss, Claudio Ronchi |
| C06-3 | Mechanics
and Material Researches on Component Design Improvements for 300MWe NPPs Yongcheng Xie, Ming Zhang, Weida Yao, Yinbiao He, Xingyun Liang, Guolin Shi, Dong Ning, Shaoxuan Lin, Yi Jing, Ren'an Yang |
| C06-4 | Hydroelasticity
and Deformations of Spacers for Fuel Elements as Structural Anisotropic Domes
Composed of Cylindrical Shells Vaclav Kuzelka |
| C06-5 | Bending
Load Analysis for the Simulator of Fuel Assembly Jing Wen, Daogang Lu, Hailong Li, Huajin Yu, Feng Sheng, Jiayi Liu |
Life
Assessment of Core Structure II
| C07-2 | A
Model for Delayed Hydride Cracking of Zirconium Alloys Young-Suk Kim, Sang-Bok Ahn, Kang S. Kim |
| C07-5 | How
the RRR Neutronic Characteristics Impact on the Mechanical Design Eduardo Villarino, Kurt Coquibus |