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Development of software for thermomechanical analysis of nuclear fuel rods in fast neutrons reactors
A. A. Sorokin, K. E. Ulibyshev, T. N. Aliev, I. A. Evdokimov, V. G. Zborovskii, V. V. Likhanskii SRC RF TRINITI
Abstract:
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.
Keywords:
fuel code, fuel rod, pellet-cladding mechanical interaction.
Received: 17.09.2012
Citation:
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”, Mat. Model., 25:4 (2013), 29–43
Linking options:
https://www.mathnet.ru/eng/mm3350 https://www.mathnet.ru/eng/mm/v25/i4/p29
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