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

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

EXPERIMENTAL STUDIES OF THE LOCAL PARAMETERS OF THE COOLANT IN THE ROD BUNDLES AT KS TEST FACILITY IN NATIONAL RESEARCH CENTER “KURCHATOV INSTITUTE” AND THEIR COMPUTATIONAL ANALYSIS

EDN: LMLULB

Authors & Affiliations

Zubkov A.G.1, Oleksyuk D.A.1, Vertikov E.A.1, Noskov A.S.1, Scherbinin A.A.1, Morozkin O.N.2, Shishkin A.A.2
1 National Research Centre “Kurchatov Institute”, Moscow, Russia
2 Join Stock Company TVEL, Moscow, Russia

Zubkov A.G.1 – Research Fellow. Contacts: 1, pl. Akademika Kurchatova, Moscow, Russia, 123182. Tel.: +7 (926) 282-56-58; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Oleksyuk D.A.1 – Head Of Department, Cand. Sci. (Tech.).
Vertikov E.A.1 – Engineer.
Noskov A.S.1 – Head Of Laboratory.
Shcherbinin A.A.1 – Deputy Head Of Department.
Morozkin O.N.2 – Project Manager.
Shishkin A.A.2 – Director Of Department.

Abstract

The paper presents the results of experimental studies of local parameters of coolant (temperature and velocity), as well as pressure drops, obtained on two multi-rod fuel assembly models. The experiments were performed at the thermal physics test facility KS in the National Research Center “Kurchatov Institute” in order to obtain data for the validation of software tools for thermohydraulic analysis of the core. The paper describes the methods of measuring local parameters. Experimental studies were carried out in a wide range of operating parameters of the coolant, in particular, at nominal operating parameters of cores of pressurized water reactors. Local temperature studies were performed using thermocouples installed in the flow, and local velocity studies were performed using Pitot tubes. The paper presents a methodology for the primary processing of experimental data. The computational analysis of the experimental data was performed using the SC-INT subchannel code. The article presents a step-by-step configuration of the input parameters of the code responsible for the characteristics of experimental fuel assembly models. A comparison of the calculated and experimental data on the magnitude of the pressure drop, local temperatures of the coolant and local speeds was performed, and a good agreement between the calculation and experiment was shown.

Keywords
thermophysical studies, local coolant parameters, fuel assemblies, fuel assembly models, pressurized water reactors, turbulent mixing, validation of subchannel codes, temperature measurement, velocity measurement

Article Text (PDF, in Russian)

References

UDC 532.57, 536.24, 621.039.5

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2025, no. 2, 2:18