18th International Conference on 
Structural Mechanics in Reactor Technology


 

DIVISION C: FUEL AND CORE STRUCTURES

 

Fuel Rod Vibration and Fretting

C01-1New Knowledge and Experiences of Flow Induced Fretting in PWR Fuel Assemblies
Juergen Stabel, Mingmin Ren, Bruno Ladouceur
C01-3Vibration Control of Nuclear Reactor Core
Ruojing Zhang
C01-6Experimental Study of Flow Induced Vibration of the Planar Fuel Assembly
Jinhua Wang, Hanliang Bo, Shengyao Jiang, Haijun Jia, Wenxiang Zheng
C01-7Fuel Rod to Support Contact Optimization for the 16x16 Next Generation Fuel
Leo Alves Carrilho

Fuel Assembly Modeling

C02-1The 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
C02-2Thermomechanical Behavior of Mexican Fabricated Fuel
Héctor Hernández López, Carlos A. Nocetti
C02-3Modeling Contacts among Multiple CANDU Fuel Elements in a Bundle
Shouze Xu, Shudong Yu, Mukesh Tayal, Zhen Xu
C02-4Improved Fuel Assembly Dynamic Model
Sudhir J. Shah, Ben Brenneman, John H. Strumpell, Gary T. Williams
C02-5Three-Dimensional Modeling of CANDU Nuclear Fuel Elements in Bowing Analysis
Shudong Yu
C02-6Analytical-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

C03-1The Fracture and Spallation of Zirconia Layers in High Burnup PWR Fuel Claddings Submitted to RIA Transients
Jean Desquines, V. Georgenthum, F. Lemoine, B. Cazalis
C03-2Development of Welded Joints for Steel and Zirconium Tubes at Nuclear Power Plants
Alexander Semenov, Vladimir Aden, Evgeny Rivkin, German Shevelyov, Vasiliy Tyurin
C03-3Analysis of Pellet-Clad Interaction of LWR Fuel Rods during Power Ramps
Ali R. Massih, Lars O. Jernkvist, Jan-Erik Lindbäck, Gang Zhou
C03-4Pellet Cladding Mechanical Interaction Assessment Using 3D Modelling
B. Michel, D. Plangcq, C. Struzik, Ph. Garcia, S. Lansiart
C03-5Influence 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

C04-1Fracture 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
C04-3Applying 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
C04-6Experimental 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
C04-7The Stress Analysis and Stress Evaluates of y-Spectrometer-Probe Station
Hailong Li

Design of Advanced Reactor Fuel

C05-1Identification of the Key Parameters Defining the Life of Graphite Core Components
Mark N. Mitchell
C05-2Theoretical 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
C05-3Experimental Study of New Generation WWER-1000 Fuel Assemblies at JSC NCCP
Anatoly A. Enin, Vladimir V. Rozhkov, Mstislav A. Shustov, Alexander P. Ustimenko
C05-4Characterization of Coated Nuclear Fuels by Nano-Indentation
Yong Choi, Bong-Goo Kim, Y.W. Lee, J.K. Lee
C05-6MP98, an Innovative Reactivity Control System for LWR and VHTR, Tests Results on Prototypes
Michel Emin, Jean Francois Gagne

Life Assessment of Core Structure I

C06-1Stress 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
C06-2Towards a Better Understanding of the Role of Stress in Restructuring of Radiation Damage
Jérome Jonnet, Paul Van Uffelen, Dragos Staicu, Thierery Wiss, Claudio Ronchi
C06-3Mechanics 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
C06-4Hydroelasticity and Deformations of Spacers for Fuel Elements as Structural Anisotropic Domes Composed of Cylindrical Shells
Vaclav Kuzelka
C06-5Bending 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

C07-2A Model for Delayed Hydride Cracking of Zirconium Alloys
Young-Suk Kim, Sang-Bok Ahn, Kang S. Kim
C07-5How the RRR Neutronic Characteristics Impact on the Mechanical Design
Eduardo Villarino, Kurt Coquibus

 

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