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

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

COMPUTATIONAL STUDY OF THREE-DIMENSIONAL COOLANT FLOW IN THE SODIUM-COOLED FAST REACTOR DURING COOLING THROUGH THE INTER-WRAPPER SPACE OF THE CORE USING THE FLOWVISION COMPUTER PROGRAM

EDN: COFFPF

Authors & Affiliations

Didenko D.V.1, Nikanorov O.L.1, Rogozhkin S.A.1, Shepelev S.F.1, Aksenov A.A.2, Zhestkov M.N.2, Shcheliaev A.E.2
1 Afrikantov Experimental Design Bureau for Mechanical Engineering, Nizhny Novgorod, Russia
2 TESIS Ltd, Moscow, Russia

Didenko D.V.1 – Design Engineer. Contacts: 15, Burnakovsky proezd, Nizhny Novgorod, Russia, 603074. Tel.: +7 (831) 246-94-31; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Nikanorov O.L.1– Head of Design Group, Cand. Sci. (Eng.).
Rogozhkin S.A.1– Head of the Department, Cand. Sci. (Eng.).
Shepelev S.F.1– Chief Designer of BN Reactor Plants, Cand. Sci. (Eng.).
Aksenov A.A.2 – Technical Director, Cand. Sci. (Phys. and Math.).
Zhestkov M.N.2 – Technical Support Center Specialist.
Shcheliaev A.E.2 – Deputy Director for Projects and Sales.

Abstract

A computational study of three-dimensional coolant flow in the sodium-cooled fast reactor during cooling through the inter-wrapper space of the core was performed using the FlowVision computer program.
Based on the FlowVision computer program, a methodical approach and a computer model were developed that allow studying the characteristics of three-dimensional coolant flow in the reactor with an acceptable accuracy using proved simplifications. The cooling process was simulated taking into account the thermal inertia of intermediate heat exchangers. The operation of autonomous heat exchangers ensuring the main heat removal during cooling was simulated using a one-dimensional mathematical model executed in the form of the program module which was connected to FlowVision. In the connected program module calculation of intermediate and air circuit of system of emergency heat removal was carried out.
Computational studies were performed for the reactor rated operation mode and cooling mode. The results obtained for the rated mode were used as the initial state for further reactor cooling mode.
The article presents the task definition, brief description of computer model and computational modes as well as the results of numerical simulation of three-dimensional coolant flow in the reactor which allowed assessing the level of temperatures in different reactor segments and tracing the process of formation of characteristic coolant circulation paths during the entire cooling process.

Keywords
computational study, FlowVision, computational fluid dynamics, CFD, heat exchange, sodium-cooled fast reactor, reactor cooling, inter-wrapper space, emergency heat removal system, computer model, integral layout, reactor core

Article Text (PDF, in Russian)

References

UDC 621.039.5:(532+536) БН+621.039.513:621.039.526

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2022, no. 3, 3:18