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

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

APPLICATION OF THE ANISOTROPIC POROUS BODY APPROXIMATION FOR STUDYING HEAT AND MASS TRANSFER PROCESSES IN BUNDLES OF RODS WITH VARIOUS SPACING METHODS COOLED BY A LIQUID METAL COOLANT

EDN: ELYAVS

Authors & Affiliations

Bayaskhalanov M.V., Merinov I.G., Kharitonov V.S., Korsun A.S.
National Research Nuclear University MEPhI, Moscow. Russia

Bayaskhalanov M.V. – Assistant. Contacts: 31, Kashirskoe shosse, Moscow, Russia, 115409. Tel.: +7 (925)  876-14-28; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Merinov I.G. – Associate Professor, Cand. Sci. (Tech).
Kharitonov V.S. – Associate Professor, Cand. Sci. (Tech).
Korsun A.S. – Associate Professor, Cand. Sci. (Tech).

Abstract

This paper presents the results of modeling the heat and mass transfer of a liquid metal coolant in rod assemblies in which spacing is carried out either using spacing grids or screw elements in the approximation of an anisotropic porous body implemented in the APMod software module.
The simulation results were compared with experimental data obtained at experimental facilities at the Karlsruhe Liquid metal Laboratory (KALLA) and at the Oak Ridge National Laboratory (ORNL). In both cases, the experiments were carried out on 19-rod assemblies, however, in the KALLA experiments, distance grids were used, and in the ORNL experiments, distance was carried out using wire wrap.
When comparing the calculated and experimental data, the possible causes of deviations were analyzed. In general, the results showed the operability of the APMod software module and its applicability for modeling heat and mass transfer in rod structures with different spacing methods.

Keywords
fast reactors, liquid metal coolants, spacer grids, wire wrapped fuel assemblies, software module based on anisotropic porous body models, numerical simulation, comparison with experimental data

Article Text (PDF, in Russian)

References

UDC 621.039

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2023, no. 2, 2:14