Authors & Affiliations

Gordeev S.S.1, Sorokin A.P.2, Tikhomirov B.B.2, Trufanov A.A.2, Denisova N.A. 2
1National Research Nuclear University “MEPHI”, Moscow, Russia
2A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia

Gordeev S.S. – graduate student, National Research Nuclear University “MEPHI”. Contacts: 31, Kashirskoe shosse, Moscow, Russia, 115409. Tel.: (967) 179 20 80, e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Sorokin A.P. – Dr. Sci. (Tech.), Deputy Director of Safety Department, A.I. Leypunsky Institute for Physics and Power Engineering.
Tikhomirov B.B. – Cand. Sci. (Tech.), Leading Researcher, A.I. Leypunsky Institute for Physics and Power Engineering.
Trufanov A.A. – Deputy Director General, Director of Safety Department, A.I. Leypunsky Institute for Physics and Power Engineering.
Denisova N.A. – Leading engineer of Safety Department, A.I. Leypunsky Institute for Physics and Power Engineering.

Abstract

The technique and algorithm for calculating the maximum temperature of fuel cladding and the nonuniformity of temperature along their perimeter, taking into account inter-channel mixing of coolant in the fuel assemblies, fuel rods fast reactors with sodium coolant based on random variation of initial parameters. The maximum rated temperature of the fuel cladding is calculated as a superposition of the mean temperature of the coolant in the surrounding channels, average perimeter shell temperature difference "semi-liquid". Running multiple thermohydraulic calculation of the statistical model of a fuel bundle and statistical processing. The results of calculations of the temperature field in the random distribution of passage sections of channels and the energy of fuel rods using the Monte Carlo method, performed according to the program MIF, which show that the average value of the maximum temperature of the fuel cladding are between the corresponding values in the model calculations tightly compressed and maximum push the beam. As averaging the values of non-uniformity of temperature along the perimeter of the fuel rods is higher than the calculation of the average parameters of the beam. The correct account of the impact of various factors, including random deviation parameters on the temperature field of fuel assemblies is a necessary requirement for modern thermal-hydraulic calculation of the fast reactor fuel assemblies.

Keywords
fast reactor, fuel subassembly, fuel element, cladding, sodium, velocity, temperature, method of calculation, computer code, interchannel mixing, random variation, model of bundle

Article Text (PDF, in Russian)

References

UDC 621.039.517.5

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants", 2016, issue 4, 4:14