Series: Nuclear and Reactor Constants

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

Authors & Affiliations

Samoilov O.B., Falkov A.A., Shipov D.L., Lukyanov V.E., Morozkin O.N.
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.
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".
Lukyanov V.E. – Lead Design Engineer, Cand. Sci. (Tech.), JSC "Afrikantov OKB Mechanical Engineering".
Morozkin O.N. – Lead Design Engineer, JSC "Afrikantov OKB Mechanical Engineering".


Thermo-hydraulic characteristics of the advanced fuel TBCA with mixing grids (TBCA-12PLUS, TBCA-T.mod.2) are presented. The results of experimental investigations of a critical heat flux on models TBCA with mixing grids are described. Calculations of characteristics TBCA with mixing grids in WWER-1000 core with the raised power and perspective WWER with power 3300 MW are executed. The estimation of increase of departure from nucleate boiling ratio due to using of mixing grids was carried out. It is shown, that using of effective mixing grids in TBCA provides increase of departure from nucleate boiling ratio and improvement of operating conditions of fuel rods due to equalizing of coolant heating and decrease of void fraction. The advanced fuel TBCA allows to provide high technical and economic characteristics of operating units WWER-1000 and perspective WWER.

fuel assembly, fuel rod, plate-type mixing grid, mixing vane, departure from nucleate boiling, critical heat flux, critical heat flux correlation, departure from nucleate boiling ratio , thermal diffusion coefficient, coolant heating, void fraction

Article Text (PDF, in Russian)


UDC 621.039.548:621.039.5

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2016, issue 3, 3:5