PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY
Series: Nuclear and Reactor Constants

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

Authors & Affiliations

Sorokin A.P., Kuzina Yu.A., Berensky L.L., Denisova N.F., Tikhomirov B.B.
A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia

Sorokin A.P. – Chief Researcher, Dr. Sci. (Tech.). Contacts: 1, Bondarenko sq., Obninsk, Kaluga region, 249033. Tel.: +7 (484) 399-84-47, e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Kuzina Yu.A. – Director of Nuclear Energetic Department, Cand. Sci. (Tech.).
Berensky L.L. – Senior Researcher.
Denisova N.A. – Lead Engineer.
Tikhomirov B.B. – Senior Researcher, Cand. Sci. (Tech.).

Abstract

A description is presented of the developed methodology and program for calculating the maximum temperature of the cladding of fuel elements and temperature irregularity along the perimeter of fuel elements in the fast reactors fuel assembly taking into account interchannel exchange with the distribution of channel cross-sections and heat generation of fuel elements according to a random law using the Monte Carlo method. Investigations of the temperature field with a random distribution of the flow cross-sections of the channels and the heat generation of the fuel elements showed that the averaged values of the maximum cladding temperature of the fuel elements are in the interval between the corresponding values for the tightly compressed and maximally extended bundle, and the averaged values of the temperature nonuniformity along the perimeter of the fuel elements are higher than when calculated using the average bundle parameters. Interchannel exchange to a certain degree aligns the temperature field on the periphery of the fuel assembly and to a large degree aligns local irregularities due to random changes in parameters. It is shown that the standard deviation of the maximum temperature of the cladding of fuel elements is 3.7% of the value (), and the standard deviation of the temperature irregularity along the perimeter of the fuel elements is 12% of the maximum temperature irregularity along the perimeter of the fuel elements in the fuel assembly. It is recommended to carry out calculations of the maximum fuel element cladding temperature using the average statistical parameters of the bundle. The dispersion of the maximum surface temperature of the fuel elements should be calculated with a general change in the flow cross sections of the channels and the heat generation of the fuel elements, and not as a superposition under the separate action of these parameters. The calculated value of the overheating factor, assessed by existing methods, should be refined using the results obtained.

Keywords
fast reactor, core, fuel assembly, fuel element, cladding, temperature, calculation method, overheating factor, interchannel mixing, heat generation, assembly model, deformation, random deviation of parameters

Article Text (PDF, in Russian)

References

UDC 621.039.534.58

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2022, issue 1, 1:12