EXPERIMENTAL RESEARCH OF THE LOCAL HYDRODYNAMICS OF COOLANT IN VVER REACTOR MIXED CORE

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Authors & Affiliations

Dmitriev S.M., Borodin S.S., Dobrov A.A., Doronkov D.V., Polozkova E.N., Pronin A.N., Sorokin V.D., Khrobostov A.E.
Nizhny Novgorod State Technical University n.a. R.E. Alekseev, Nizhny Novgorod, Russia

Dmitriev S.M. - Rector, Dr. Sci. (Tech.), Professor, Nizhny Novgorod State Technical University n.a. R.E. Alekseev. Contacts: 24, Minina st., Nizhny Novgorod, Russia, 603950. Tel.: (831) 436-93-24; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it.
Khrobostov A.E. – Director of INI and T, Cand. Sci. (Tech.), Assistant Professor, Nizhny Novgorod State Technical University n.a. R.E. Alekseev.
Borodin S.S. – Deputy director of INI and T, Cand. Sci. (Tech.), Assistant Professor, Nizhny Novgorod State Technical University n.a. R.E. Alekseev.
Sorokin V.D. – Assistant, Nizhny Novgorod State Technical University n.a. R.E. Alekseev.
Dobrov A.A. – PhD student, Nizhny Novgorod State Technical University n.a. R.E. Alekseev.
Doronkov D.V. – PhD student, Nizhny Novgorod State Technical University n.a. R.E. Alekseev.
Pronin A.N. – PhD student, Nizhny Novgorod State Technical University n.a. R.E. Alekseev.
Polozkova E.N. – Master Student, Nizhny Novgorod State Technical University n.a. R.E. Alekseev.

Abstract

Results of researches of interassembly interaction of coolant flow in VVER-1000 core of Atomic Power Station “Temelin”. Study of coolant flow process in fuel element bundle FA has been carried out on an aerodynamic experimental rig. VVER-1000 core fragment which consists of FA-12 PLUS and FA-T with stiffening angles and interassembly gap has been chosen as a model to receive more detailed information on hydrodynamic characteristics of coolant flow. Investigations of hydrodynamic characteristics of coolant have been consisted in measuring coolant flow velocity vector as in chara cteristic zones areas of FA, as in interassembly gap by means of the five-channel pneumometric probe. An analysis of spatial distribution of absolute velocity flow projections allowed to specificate pattern (picture) of flow-past spacer and mixing grids and combined spacer grids of FA, to determine realization zones of maximum cross-flow of coolant, depth of disturbance passage and redistribution of coolant rate in neighboring assemblies of FA. Investigation results of interassembly interaction of coolant between neighboring FAs are used in Afrikantov OKBM JSC to specify methods of hydraulic design VVER-1000 cores and have been included in a data-base for verifying CFD codes (Computation Fluid Dynamics) and for detailed cell-wise calculation VVER-1000 reactor cores.

Keywords
core, fuel assemblies, spacer and mixing grids, interassembly interaction, coolant hydrodynamics

Article Text (PDF, in Russian)

References

1. Dmitriev S.M., Zverev D.L., Byh O.A., Panov Yu.K., Sorokin N.M., Farafonov V.A. Osnovnoe oborudovanie AES s korpusnymi reaktorami na teplovykh nejtronakh [The main equipment of nuclear power plants with a tank reactor with thermal neutrons]. Moscow, Mashinostroenie Publ., 2013. 415 p.

2. Barinov A.A., Borodina V.E., Dmitriev S.M., Hrobostov A.E. K voprosu o metodologii obosnovaniya teplotekhnicheskoy nadezhnosti aktivnykh zon vodyanykh energeticheskikh reaktorov [On the issue of core cooling reliability substantiation methodology for the pressurized water reactors]. Trudy NGTU im. R.E. Alekseeva – Transactions of NNSTU n.a. R.E. Alekseev, 2014, no. 2(104), pp. 98-108.

3. Dmitriev S.M., Borodin S.S., Legchanov M.A., Solncev D.N., Sorokin V.D., Hrobostov A.E. Eksperimental'nye issledovaniya gidrodinamicheskikh i massoobmennykh kharakteristik potoka teplonositelya v TVSA VVER [Experimental studies of hydrodynamic and mass-transfer properties of coolant flow in VVER fuel assemblies TVSA]. Atomnaya energiya – Atomic Energy, 2012, vol. 113, no. 5, pp. 252-257.

4. Dmitriev S.M., Varencov A.V., Dobrov A.A., Doronkov D.V., Samojlov O.B., Sorokin V.D., Hrobostov A.E. Raschetno-eksperimental'nye issledovaniya lokal'noy gidrodinamiki i massoobmena potoka teplonositelya v TVS-Kvadratreaktorov PWR s peremeshivayushchimi reshetkami [Combined numerical and experimental investigations of local hydrodynamics and coolant flow mass transfer in Kvadrat type fuel assemblies of PWR reactors with mixing grids]. Teploenergetika – Thermal Engineering, 2014, no. 8, pp. 20-27.

5. Zhukov A.V., Sorokin A.P., Matyukhin N.M. Mezhkanalnyiy obmen v TVS byistryikh reaktorov: Teoreticheskie osnovyi i fizika protsessa [Interchannel Transfer in Fuel Assemblies of Fast Neutron Reactors: Theoretical Principles and Physics of the Process]. Moscow, Energoatomizdat Publ., 1989. 130 p.

6. Borodin S.S., Dmitriev S.M., Legchanov M.A., Solntsev D.N., Sorokin V.D., Khrobostov A.E. Osobennosti lokal'noy gidrodinamiki i massoobmena teplonositelya v TVS reaktorov VVER i PWR s peremeshivayushchimi reshetkami [Features of local hydrodynamics and mass exchange of the heatcarrier in fuel rod assemblies of VVER and PWR with mixing grids]. Teplovye protsessy v tekhnike – Thermal Processes in Engineering, 2013, vol. 5, no. 3, pp. 98-107.

UDC 621.039

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2016, issue 3, 3:8

BROND-3.1

ISSUES

EXPERIMENTAL RESEARCH OF THE LOCAL HYDRODYNAMICS OF COOLANT IN VVER REACTOR MIXED CORE