Calculation of the thermohydraulic parameters of a core comprised of unjacketed fuel assemblies |
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Authors: | S Yu Zakirov |
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Affiliation: | (1) Slovak University of Technology, Ilkovičova 3, 81219 Bratislava, Slovakia |
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Abstract: | A computer program for calculating the thermohydraulic parameters of a core with jacketless fuel assemblies as a single mass
of fuel elements is developed on the basis of the Kedr program for the channelwise computation. The Kedr-A program algorithm
employs the principle of decomposition (partition) to the computed region of the core (1/12th part). The computational space
is divided into a definite number of subregions – symmetry elements with repeatable geometric structure of the lattice of
fuel elements and other structural components of the core. The thermohydraulic parameters of the cells in each section of
the core are calculated iteratively over the symmetry elements of the jacket-less fuel assemblies of 1/12th part of the core
of a nuclear reactor with water coolant. The symmetry elements are interrelated by the conditions at the boundaries connecting
theses regions. The computational algorithm is checked by comparing with experimental data on the mixing of the coolant obtained
on a technological stand consisting seven jacketless fuel assemblies. |
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