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

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

MODIFIED VERSION OF THE TFEDM22 CALCULATION PROGRAM

EDN: EWRUVO

Authors & Affiliations

Alekseev P.A., Pyshko A.P., Ruzhnikov V.A., Ivanov A.S.
A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia

Alekseev P.A. – Senior Researcher, Cand. Sci. (Tech.). Contacts: 1, pl. Bondarenko, Obninsk, Kaluga region, Russia, 249033. Tel.: +7 (484) 399-70-00 (add 41-61); e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Pyshko A.P. – Head of Department, Cand. Sci. (Phys.-Math.).
Ruzhnikov V.A. – Candidate of Engineering Sciences, Leading Researcher. Cand. Sci. (Tech.).
Ivanov A.S. – Research Engineer.

Abstract

The article provides a brief description and results of calculations carried out using the modified version of the TFEDM22 calculation program. TFEDM22 is developed to evaluate the thermal and electro-physical characteristics (TEC) of the thermionic fuel element (TFE) reactor-converter. In addition to traditional heat transfer tasks, TFEDM22 implements heat transfer due to thermionic current, making this code unique.
The modification of TFEDM22 involved implementing the capability to use point-wise distribution of power release along the height of the TFE, directly obtained from neutron-physical calculations. In the unmodified TFEDM22 code, the distribution of power release along the height of the reactor is restored using a cosine function with the application of the kz value.
The necessity for this modification is driven by the use of means to equalize power release along the reactor's height, leading to significant deviations in the power release distribution shape from the cosine function shape.
The results of the comparative calculations show that using the cosine function to restore the power release distribution can overestimate the electric power values by 2 to 25 %.
This modification allowed the creation of an optimization code for selecting the lengths of termionic fuel element, integrating neutron-physical and thermal and electrophysical calculation programs with optimization algorithms. As an optimization method, a genetic algorithm was used, which has proven itself well in solving problems of optimizing the core and radiation shield of a thermionic nuclear power unit.
The calculations showed that the developed optimization code finds solutions that are no worse than the currently used method. Additionally, since the entire process is automated, the time required to find such a solution is reduced.

Keywords
thermoelectrophysical calculation, power release distribution shape, geometric optimization of TFE, genetic algorithm

Article Text (PDF, in Russian)

References

UDC 621.039.578:629.7

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2025, no. 1, 1:5