19th International Conference on 
Structural Mechanics in Reactor Technology


 

Division C: Computational Mechanics and
Computing Applications


Coordinators

Sylvain Leclercq, Electricite de France

American Correspondents
Joseph Lau, Atomic Energy of Canada, Limited (AECL)
K.L. Murty, NC State University

 

C01: Computer Aided Engineering

C01/1

Creep Behavior of Niobium-Containing Zirconium Alloys – An Overview
I. Charit, K. L. Murty

C01/2

Cladding Tube Testing in Creep Conditions under Multiaxial Loadings: A New Device and Some Experimental Results
C. Grosjean, D. Poquillon, J.-C. Salabura, J.-M. Cloué

C01/3

A Numerical Model for Delayed Hydride Cracking of Zirconium Alloy Cladding Tubes
L.O. Jernkvist. A.R. Massih

C01/4 A Model to Describe the Anisotropic Viscoplastic Mechanical Behavior of Fresh and Irradiated Zircaloy-4 Fuel Claddings under RIA Loading Conditions
M. Le Saux, C. Poussard, X.. Averty, S. Carassou, J.Besson
C01/5 A Generalized Failure Map for Fuel Elements Subject To a Power Pulse
J.C.Luxat, D. R. Novog
   

C02: Experimental Methods of Cladding Characterization

 

C02/1

High Temperature Deformation Characteristics of Zirlo Tubing via Ring Creep and Burst Tests
C.S. Seok, B. Marple, G. Srikant, I. Charit, K.L. Murty

C02/2

Failure Characteristics of Cladding Tubes under RIA Conditions Through Electromagnetic Forming
M. Leroy, A. Parrot, S. Leclercq

C02/3

Evaluation of An-isotropy of Pilgered Zirconium Alloys by Neutron Scattering and Its Effect on Hydride Formation and Corrosion Behavior
M. Kim, Y. Choi, J.W. Choi, S.C. Kwon

C02/4

Theoretical and Experimental Modeling of the Multiple Pressure Tube Rupture for RBMK Reactor. Part III
N. Yu. Medvedeva, A.V. Andreev, V.N. Zhilko, D.Y. Martsiniouk

C02/5

Experimental Simulation of the Paks-2 Cleaning Tank Incident
Z. Hózer, P. Windberg, I. Nagy, A. Vimi, N. Vér, L. Matus, M. Kunstár

 
C03: Fuel Assembly Behaviour Under Normal and Accidental Conditions
 
C03/1 An Investigation on the Holddown Margin using Monte-Carlo Algorithm for the PWR Fuel Assembly
S. Jeon, N.G. Park, G.T. Choi, H.K. Kim

C03/2

The Buckling of Fuel Rods under Inertia Loading
G.S. Bjorkman
C03/3 Assemblies Behaviour Under Thermal Mechanical Loading
A.S. Kiselev, A.S. Kiselev, A.A. Tutnov
C03/4 Finite Element Prediction of End Cap Stresses Under Accident Conditions
L. Jiang, H. Sills, K. MacKay, R. Gibb
 
C04: Fuel Behaviour and Performance
 
C04/1 Application of "Fitness For Service" Concept to Evaluation of CANDU Fuel Performance
A. Viktorov, M. Couture, H.C. Suk
C04/2 Analysis of Thermal Conductivity of Irradiated UO2 Fuel
A.V. Palagin
C04/3 Overall Viscoplastic Behaviour of Uranium Dioxide
J.-M. Gatt, J.-C. Menard
C04/4 Stress in End Fitting Grayloc Connection due to Flame Heating for Cap Screw Removal
S-H. Kim, S.S. Ho, D. Vlaicu
C04/5 Mathematical Modeling of Pencil-Thin Nuclear Fuel Rods
V. Zozulya
 
C05: Dynamics and Seismic Analysis
 
C05/1 A Repeated Dynamic Impact Analysis for 7 x 7 Spacer Grids using ABAQUS/Standard and Explicit
J.-Y. Kim, K.-H. Yoon
C05/2 Axial Impact Analysis of a 16 by 16 Fuel Assembly by FE Method
K. Yoon, C. Ahn, H. Kim, T. Chun
C05/3 Fuel Transient Behavior Analysis
G. Negut, I. Prisecaru, D. Dupleac
C05/4 Results of the LIVE-L2 Experiment on Melt Behaviour in RPV Lower Head Performed Within the LACOMERA Project at the Forschungszentrum Karlsruhe
A. Miassoedov, T. Cron, J. Foit
C05/5 Uncertainties in the No Lift-off Criterion Used in Fuel Rod Assessment
A. Yaméogo, B. Sudret, S. Cambier
 
Workshops WC: Advanced Reactor Fuel and Cladding Materials
 
WC1/1 Overview of GenIV Reactor Materials Issues
W. Corwin
WC1/2 Materials for Very High Temperature Gas-Cooled Reactors
K. Smit
WC1/3 High Temperature Materials and Design Issues for GenIV Reactors
T. McGreevy

 

 

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