Authors & Affiliations
Sorokin A.P.1, Sorokin G.A.2, Kuzina Yu.A.1, Denisova N.A.1
1 A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia
2 Moscow Institute of Physics and Technology (National Research University), Moscow, Russia
Sorokin A.P.1 – Chief Researcher, Dr. Sci. (Tech.). Contacts: 1, pl. Bondarenko, Obninsk, Kaluga region, Russia, 249033. Tel.: +7 (484) 399-70-00 (add. 84-47); e-mail:
Kuzina Yu.A.1 – Head of Department of Nuclear Power Engineering, Cand. Sci. (Tech.).
Denisova N.A.1 – Lead Engineer..
Sorokin G.A.2 – Associate Professor, Cand. Sci. (Tech.).
Abstract
The operating temperature of fuel elements is determined by a large number of factors of regular and stochastic nature. Research to substantiate the operating temperature modes of fuel elements and fuel assembly covers in the core of fast neutron reactors is aimed at studying the influence of various factors on the thermal hydraulics of fuel assemblies, optimizing the design of fuel assemblies in order to achieve high burn up of nuclear fuel, improve reliability and increase service life. The article presents a methodology and description of the implementation of computational modeling of the operating temperature regimes of fast reactors, including the calculation of hydraulic throttling, distribution of the velocity and temperature of the coolant in the fuel assemblies taking into account the change in the shape of the bundle of fuel elements and fuel assemblies, thermomechanical calculation of the temperature distribution and the stress-strain state of the fuel element cladding during the campaign. The article presents data from a review of various factors influencing the formation of operating temperature modes of fuel elements and covers in the fuel assemblies. The effect of various design, regime and operational factors and their deviations from nominal values on the temperature regime of fuel elements is shown. Due to the composition of local and global overheating of the fuel element cladding and the fuel assembly jacket due to the simultaneous effect of various factors, the total value of the fuel element cladding overheating can be 15–20 % of the average heating in the fuel assembly at the beginning of the campaign and up to 50–100 % with a significant change in the shape of the fuel assembly at the end of the campaign. Uncertainty in the values of the initial parameters and calculation constants, mainly the coolant flow through the fuel assembly, the energy release of the fuel elements and the distribution of geometric parameters, causes uncertainty in the values of the maximum fuel element cladding temperature of up to 10 % of the average heating of the coolant in the fuel assembly and the maximum azimuthal non-uniformity of temperature of up to 30 % of its absolute value. A significant factor in the formation of temperature fields in the fuel assembly is interchannel exchange, which effectively equalizes local non-uniformities in the coolant temperature in the fuel assembly, which leads to a decrease in the maximum temperature of the fuel element cladding and the azimuthal non-uniformity of the fuel element temperature.
Keywords
fast reactors, liquid metals, calculation methods, experiment, thermal hydraulics test, reactor core, fuel assembly, fuel element, factors, parameter distribution, stochastic, energy release, geometry, campaign, deformation, radiation effects, temperature, heating of coolant
Article Text (PDF, in Russian)
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UDC 536.24:621.039.524.4:621.039.58
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2026, no. 2, 2:18