EDN: EPPKWR
Authors & Affiliations
Dmitriev S.M., Dobrov A.A.
Nizhniy Novgorod State Technical University n.a. R.E. Alekseev, Nizhniy Novgorod, Russia
Dmitriev S.M. – Rector, Professor, Dr. Sci. (Tech.);
Dobrov A.A. – Junior Researcher. Contacts: 24, Minina st., Nizhny Novgorod, Russia, 603950. Tel.: +7 (831) 436-80-17; e-mail:
Abstract
The purpose of this work was to carry out numerical simulation of the coolant flow in the model of the inlet section of a cassette fuel assembly using the LOGOS computational fluid dynamics program, as well as to formulate, based on the obtained results, the boundary conditions for the distribution of coolant flow rates in the cells at the entrance to the fuel bundle for the subchannel program for thermal-hydraulic analysis of the reactor core.
The article presents the developed automated algorithm for processing CFD simulation data in the LOGOS program, as a result of which the values of the coolant velocities in the cross section corresponding to the beginning of the active part of the fuel bundle in all subchannels were obtained. The obtained data were automatically processed and used as an input boundary condition for the subchannel calculation of the core.
The article shows that the substitution of a realistic velocity profile at the entrance to the calculated subchannel model of the fuel assembly, obtained from the results of the CFD calculation, made it possible to significantly reduce the inaccuracy in determining the coolant flow rate for the subchannels of the model, which in turn leads to an increase in the accuracy and reliability of the calculation other thermal parameters.
Keywords
computational fluid dynamics, fuel assembly, LOGOS, core, subchannel calculation, RITM-200, inlet section, coolant, fuel bundle, nuclear reactor, coolant flow rate
Article Text (PDF, in Russian)
UDC 621.039
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2023, no. 2, 2:19