Geodesic
Development of software for thermomechanical analysis of nuclear fuel rods in fast neutrons reactors
Matematičeskoe modelirovanie, Tome 25 (2013) no. 4, pp. 29-43.

Voir la notice de l'article provenant de la source Math-Net.Ru

The computer code RTOP-M is created to model the mechanical interaction of fuel with a cladding in fast neutrons reactors. The brief description of models of the RTOP-M code is provided in the work. The results of test calculations of mechanical stresses and strains in the cladding are given for problems with different geometries.
Mots-clés : fuel code
Keywords: fuel rod, pellet-cladding mechanical interaction. 
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     author = {A. A. Sorokin and K. E. Ulibyshev and T. N. Aliev and I. A. Evdokimov and V. G. Zborovskii and V. V. Likhanskii},
     title = {Development of software for thermomechanical analysis of nuclear fuel rods in fast neutrons reactors},
     journal = {Matemati\v{c}eskoe modelirovanie},
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     url = {http://geodesic.mathdoc.fr/item/MM_2013_25_4_a2/}
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A. A. Sorokin; K. E. Ulibyshev; T. N. Aliev; I. A. Evdokimov; V. G. Zborovskii; V. V. Likhanskii. Development of software for thermomechanical analysis of nuclear fuel rods in fast neutrons reactors. Matematičeskoe modelirovanie, Tome 25 (2013) no. 4, pp. 29-43. http://geodesic.mathdoc.fr/item/MM_2013_25_4_a2/

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