Published July 2005 | Version v1
Book

Influence of azimuth and radial neutron and thermal sources anisotropy on contact problem simulation in real fuel pellet-cladding configuration using FEM

  • 1. Nuclear Research Institute Rezplc (Czech Republic)

Description

Paper summarises results of development and testing effort to model 2D and 3D nonsymmetric contact problem between fuel pellet and cladding using FEM. Interface between neutron and thermo-mechanical calculation models will be described. Corrosion layers and irradiation induced material properties degradation are treated in problem solution as well. Special interface programme for surface and volumetric source automatic input into the FEM COSMOS/M system was developed. Discussion of qualitative analysis of the results obtained by the new system using parametric simulation will be presented with accent to the contact problem solution and the stress-strain field distribution in contact regions. Conclusions will be given for the further development effort and validation approach will be presented. (authors)

Part of:
Proceedings of 18th international conference on structural mechanics in reactor technology

Additional details

Publishing Information

Publisher
Atomic Energy Press
Imprint Place
Beijing (China)
ISBN
7-5022-3421-7
Imprint Title
Proceedings of 18th international conference on structural mechanics in reactor technology
Imprint Pagination
4896 p.
Journal Page Range
p. 488-500

Conference

Title
18. international conference on structural mechanics in reactor technology
Dates
7-12 Aug 2005
Place
Beijing (China)

Optional Information

Notes
13 figs., 2 tabs., 7 refs.