Computational-Experimental Investigations of the Processes of Motion of a Coolant Flow in the Region of the Guide Channel Behind Mixing Grids of Fuel Assemblies

Герасимов, А. В.; Dmitriev, S. M.; Dobrov, A. A.; Doronkov, D. V.; Pronin, A. N.; Ryazanov, A. V.; Solntsev, D. N.; Khrobostov, A. E.

doi:10.1007/s10891-020-02102-x

Cited by 1 publication

(1 citation statement)

References 1 publication

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The coolant flow in the core was modeled using a wind tunnel test facility (Gerasimov et al 2020, Samoylov et al 2019, Dmitriyev et al 2014a, 2018, Varentsov et al 2012.…”

Section: Test Facilitymentioning

confidence: 99%

Experimental investigation of the coolant flow in the VVER reactor core with TVSA fuel assemblies

Dmitriyev¹,

Герасимов²,

Dobrov³

et al. 2021

NUCET

View full text Add to dashboard Cite

The paper presents the results of an experimental study to investigate the coolant interaction in adjoining fuel assemblies in the VVER reactor core composed of TVSA-T and upgraded TVSA FAs. The processes of the in-core coolant flow were simulated in a test wind tunnel. The experiments were conducted using models representing different portions of the VVER reactor core fuel bundle and consisted in measuring the radial and axial airflow velocities in representative areas within the FAs and in the interassembly space. The results of the experiments can be translated to the full-scale conditions of the coolant flow with the use of the fluid dynamics simulation theory. The measurements were performed using a five-channel pressure-tube probe. The coolant flow pattern in different portions of the fuel bundle is represented by distribution diagrams and distribution maps for the radial and axial velocity vector components in the representative areas of the models. An analysis for the spatial distribution of the radial and axial velocity vector components has made it possible to obtain a detailed pattern of the coolant flow about the FA spacer, mixing and combined spacer grids of different designs. The accumulated database for the coolant flow in FAs of different designs forms the basis for the engineering justification of the VVER reactor core reliability and serviceability. The investigation results for the coolant interaction in adjoining TVSA FAs of different designs have been adopted for the practical use at JSC Afrikantov OKBM to estimate the heat-engineering reliability of the VVER reactor cores and have been included in the database for verification of computational fluid dynamics (CFD) codes and detailed by-channel calculation codes.

show abstract

“…The coolant flow in the core was modeled using a wind tunnel test facility (Gerasimov et al 2020, Samoylov et al 2019, Dmitriyev et al 2014a, 2018, Varentsov et al 2012.…”

Section: Test Facilitymentioning

confidence: 99%