RUS  ENG
Full version
JOURNALS // Matematicheskoe modelirovanie // Archive

Matem. Mod., 2013 Volume 25, Number 4, Pages 29–43 (Mi mm3350)

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.

UDC: 621.039.548

Received: 17.09.2012



© Steklov Math. Inst. of RAS, 2024