Izvestiya vuzov. Yadernaya Energetika

The peer-reviewed scientific and technology journal. ISSN: 0204-3327

Using the ISTAR Code to Solve Problems of the Molten Salt Fuel Nuclide Composition Change

12/20/2024 2024 - #04 Modelling processes at nuclear facilities

Blandinskiy V.Y. Dudnikov A.A. Kuzenkova D.S. Subbotin S.A.

DOI: https://doi.org/10.26583/npe.2024.4.11

UDC: 621.039.5

The paper considers the computational capabilities of the ISTAR code, which allows one to proceed from considering the solution of time-dependent problems that describe the change in the isotopic composition in the neutron field and in the process of decay cooling, involved in calculation of specific nuclear facility models, to analyzing system problems of estimating equilibrium quantities of nuclides, which can be accumulated,in principle, both in a separate nuclear facility and in a nuclear energy system. The ISTAR code is designed for investigating computationally complex structures of nuclear energy systems, including nuclide transformation in different nuclear energy system components: nuclear reactors, spent fuel storage facilities, fuel reprocessing and fabrication plants, etc., and nuclide flows between them. Calculations can be undertakenboth for steady-state modes (equilibrium state) and for non-steady-state modes (burnup and decay modes). The paper describes the capabilities of the ISTAR code and demonstrates these using an example with calculation of the nuclide composition change in the molten salt blanket of a thermonuclear neutron source. The cross-verification results are also presented in comparison with calculations based on the Serpent and JARFR codes. Results are presented from the isotopic composition evolution simulation in a test problem. The achievement of equilibrium concentrations is demonstrated in the test problem considered. The ISTAR code helps one potentially to resolve issues involved in developing further nuclear power as a system in conditions with a fundamental uncertainty of both the performance of innovative reactors and nuclide flows between different components of the nuclear fuel cycle. At the same time, it becomes possible to estimate the neutron potential of each nuclide in the system when using them in different reactor types.

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ISTAR thermonuclear neutron source TNS neutronic performance

Link for citing the article: Blandinskiy V.Y., Dudnikov A.A., Kuzenkova D.S., Subbotin S.A. Using the ISTAR Code to Solve Problems of the Molten Salt Fuel Nuclide Composition Change. Izvestiya vuzov. Yadernaya Energetika. 2024, no. 4, pp. 128-143; DOI: https://doi.org/10.26583/npe.2024.4.11 (in Russian).

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