Development of the code CYCLE for nuclear fuel cycle analysis

3/28/2016 2016 - #01 Fuel cycle and nuclear waste management

Kalashnikov A.G. Moseev A.L. Dekusar V.M. Korobeynikov V.V. Moseev P.A.

https://doi.org/10.26583/npe.2016.1.10

The software package CYCLE was designed for mathematical modeling of the nuclear fuel cycle, the development of scenarios efficient development of nuclear power in Russia and for analysis of global trends in the nuclear power industry. It is based on well known tool - WIMSD-5B widely used for the thermal reactor cells calculations and on the two - dimensional multigroup code - RZA for the fast reactor simulation. The code CYCLE was designed in the State Scientific Center of RF «Institute for Physics and Power Engineering (IPPE)», Obninsk. The first phase of the code CYCLE options is in the paper [1]. This paper contains the short review of computer code CYCLE possibilities. This code allows to model the main fuel cycle facilities (fabrication and reprocessing, spent nuclear fuel interim storage, stocks of uranium, plutonium, neptunium, americium, curium and final repository), thermal and fast nuclear reactors, including RBMK-1000, current and advanced VVER (with different fuel types, i.e. UOX, MOX), FBRs (current and innovative). The important feature of code CYCLE is the careful consideration of the evolution of the fuel composition inside of the reactors and on the outside stages of fuel cycle. The additional option of the code is the calculation of certain cost parameters of the closed nuclear fuel cycle for nuclear power plants with fast and thermal reactors. For many years this code has been successfully used in the international research project on Innovative Nuclear Reactors and Fuel Cycles - INPRO. The calculation results of modeling studies of Russian NPP development scenarios with time variation of introduction of fast reactors into nuclear energy system were presented at Global-2011 conference. Some other simulation results with code CYCLE were presented at the Global-2015 conference.

Ссылки

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12. Dekusar V.M., Egorov A.F., Kalashnikov A.G., Korobejnikov V.V., Korobicyn V.E., Moseev A.L., Moseev P.A. Modelirovanie raboty mezhdunarodnogo jadernogo toplivnogo centra po predostavleniju uslug stranam blizhnego zarubezh’ja. [Simulation of the International Nuclear Fuel Center Operation]. Izvestia vuzov. Yadernaya energetika. 2014, no. 1, pp. 121-132 (in Russian).
13. Kagramanyan V., Usanov V., Kalashnikov A., Kvyatkovskii S. «Medium-term Nuclear Industry Prospects Associated with Synergistic LWR/SFR System and Related Closed Nuclear Fuel Cycle», Proceedings of Global 2015, Paris (France), September 20-24, 2015, Paper 5115.

nuclear fuel cycle simulation computer code scenario fast reactor enrichment isotopic composition plutonium equivalence function storage storage topology

Link for citing the article: Kalashnikov A.G., Moseev A.L., Dekusar V.M., Korobeynikov V.V., Moseev P.A. Development of the code CYCLE for nuclear fuel cycle analysis. Izvestiya vuzov. Yadernaya Energetika. 2016, no. 1, pp. 91-99; DOI: https://doi.org/10.26583/npe.2016.1.10 (in Russian).