Authors & Affiliations

Samoilov O.B., Kupriyanov A.V., Falkov A.A., Shipov D.L., Molodtsov A.A., Lukyanov V.E.
JSC "Afrikantov OKB Mechanical Engineering", Nizhny Novgorod, Russia

Samoilov O.B. - Chief Designer, Dr. Sci. (Tech.), JSC "Afrikantov OKB Mechanical Engineering". Contacts: 15, Burnakovsky proyezd, Nizhny Novgorod, Russia, 603074. Tel: (831)275-26-40; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it.
Kupriyanov A.V. – Deputy Head of Department, Can. Sci. (Tech.), JSC "Afrikantov OKB Mechanical Engineering".
Falkov A.A. – Deputy Head of Department, Cand. Sci. (Tech.), JSC "Afrikantov OKB Mechanical Engineering".
Shipov D.L. – Head of Bureau, Cand. Sci. (Tech.), JSC "Afrikantov OKB Mechanical Engineering".
Molodtsov A.A. – Head of Bureau, Cand. Sci. (Tech.), JSC "Afrikantov OKB Mechanical Engineering".
Lukyanov V.E. – Lead Design Engineer, Cand. Sci. (Tech.), JSC "Afrikantov OKB Mechanical Engineering".

Abstract

Results of experimental investigations of the advanced fuel assembly ÒÂÑÀ with mixing grids (TBCA-12PLUS, TBCA-T.mod.2) are presented. The experimental equipment and results of experimental investigations of a critical heat flux on models ÒÂÑÀ with mixing grids are described. The experimental investigations were conducted on 19-rod models TBCA with three intermediate mixing grids including models with uniform and non-uniform axial heating. On the basis of the obtained experimental data for ÒÂÑÀ with mixing grids the correlation for critical heat flux calculation is developed and the thermal diffusion coefficient is determined. The validation results of subchannel thermo-hydraulic code KANAL for coolant local temperatures and critical heat flux in ÒÂÑÀ with mixing grids are presented.

Keywords
fuel assembly, mixing grid, mixing vane, fuel rod simulator, departure from nucleate boiling, critical heat flux, critical heat flux correlation, thermal diffusion coefficient, coolant heating, void fraction

Article Text (PDF, in Russian)

References

UDC 621.039.548:621.039.5

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants", 2016, issue 3, 3:4