Authors & Affiliations
Kriachko M.V.1, Zabrodskaia S.V.1, Semenov M.Yu.1, Khomyakov Yu.S.2
1 A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia
2 ROSATOMS’s "Innovation and technology center for the "PRORYV" project", Moscow, Russia
Kriachko M.V. – Researcher, A.I. Leypunsky Institute for Physics and Power Engineering. Contacts: 1, pl. Bondarenko, Obninsk, Kaluga region, Russia, 249033. Tel.: +7(484) 399-80-45; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Zabrodskaia S.V. – Head of Laboratory, Cand. Sci. (Phys.-Math.), A.I. Leypunsky Institute for Physics and Power Engineering.
Semenov M.Yu. – Leading Researcher, Cand. Sci. (Phys.-Math.), A.I. Leypunsky Institute for Physics and Power Engineering.
Khomyakov Yu.S. – Head of the Department of Scientific Leader of Research and Development, Dr. Sci. (Phys. Math.), ROSATOMS’s "Innovation and technology center for the "PRORYV" project".
Abstract
One of the most important tasks in the design, operation of nuclear power plants and fuel cycle facilities is the justification of radiation safety at various stages of fuel handling.
In the practice of R&D related to the fuel cycle of nuclear reactors, there is often a need for a multitude of calculations of the isotopic composition of fuel assemblies irradiated in different parts of the reactor core. In this case, it is often important to take into account the influence of the axial distribution of the neutron flux on the isotopic composition of SNF, that is, it is necessary to divide each fuel assembly into calculated areas along its axis. All this can significantly increase the number of calculation options that need to be carried out.
Also, for the purposes of cross-verification, it becomes necessary to calculate these variants for various isotopic kinetics programs. All this leads to the need to prepare a large number of computational tasks for isotopic kinetics programs associated with neutron-physical calculations, which, firstly, is a very laborious task, and secondly increases the probability of errors.
The FURCAN software complex is developed at the IPPE and is intended for calculations of the isotope composition and radiation characteristics of fresh and irradiated nuclear fuel. The purpose of creating a software package is to optimize the calculation of isotope kinetics during irradiation and exposure to fuel.
This paper presents the description and structure of the FURCAN software package, and presents the results of calculations of the isotopic composition of fuel samples irradiated in BN-350.
Keywords
software package, isotopic composition calculation, nuclear fuel cycle, irradiated fuel
Article Text (PDF, in Russian)
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