Modeling the process of mixing the coolant in the lower section and pressure mixing chamber of VVER-1200 (V-491)-Reference-Cited by-同舟云学术

Modeling the process of mixing the coolant in the lower section and pressure mixing chamber of VVER-1200 (V-491)

Published:2022-04-07 Issue:1 Volume:67 Page:65-74
ISSN:2524-244X
Container-title:Proceedings of the National Academy of Sciences of Belarus, Physical-Technical Series
language:
Short-container-title:Vescì Akademìì navuk Belarusì. Seryâ fizika-tehničnyh navuk

Author:

Chorny A. D.¹^ORCID,Mikheenko S. D.²^ORCID,Speransky P. A.³^ORCID,Mostovenko A. L.²^ORCID,Krysin A. I.²^ORCID,Baranova T. A.¹^ORCID,Zhukova Yu. V.¹^ORCID,Kukharchuk I. G.¹^ORCID

Affiliation:

1. A. V. Luikov Heat and Mass Transfer Institute of the National Academy of Sciences of Belarus

2. Center for Nuclear and Radiation Safety

3. Institute for Nuclear Problems of Belarusian State University

Abstract

The most representative accident scenario is determined and a physical and mathematical model is developed for studying the mixing of non-isothermal coolant flows in the structural elements of the V-491 reactor facility (VVER-1200), in which the motion of the medium is described in a three-dimensional non-stationary formulation. Based on the analytical estimates of the list of initiating events, a scenario was chosen with the connection of an idle loop of the main circulation pipeline to three operating ones without a preliminary power reduction. A computational algorithm and a numerical method have been developed for the computational analysis of the selected accident scenario and the justification of the safety of operation of the V-491 reactor facility (VVER-1200). During the numerical simulation, the RANS method was used, which consists in solving the Reynolds-averaged Navier–Stokes equations, the continuity equation and the energy equation. The SST k–ω model of turbulence by Florian Menter is used to close the equations. The verification of the developed physical and mathematical model and calculation procedure was carried out by modeling thermohydraulic processes in models with both a relatively simple geometric design (tee connection) and in a scale model of the reactor vessel (ROCOM experiment), including a lowering section and a pressure mixing chamber. The qualitative agreement of the numerical simulation results with the available data of physical experiments is shown. The results of numerical simulation of the mixing process of non-isothermal coolant flows in the section from the branch pipe of the “cold” thread of the main circulation pipeline to the lower boundary of the fuel of the VVER-1200 core (V-491) are presented. It is shown that the heterogeneity in the temperature distribution at the entrance to the core manifests itself up to 15.5 s of the calculated accident scenario. For calculations the following code coupling were used: Ansys Fluent/Rainbow-TPP.

Publisher

Publishing House Belorusskaya Nauka

Subject

Pharmacology (medical)

Reference11 articles.

1. Andrushechko S. A., Afrov A. M., Vasiliev B. Yu. NPP with a WWER-1000 Type Reactor. From the Physical Foundations of Operation to the Evolution of the Project. Moscow, Logos Publ., 2010. 604 p. (in Russian).

2. Barinov A. A., Dmitriev S. M., Khrobostov A. E., Samoilov O. B. Methods of Thermomechanical Reliability Validation of Thermal Water-Moderated and Water-Cooled Reactor Cores. Atomic Energy, 2016, vol. 120, no. 5, pp. 335– 341. https://doi.org/10.1007/s10512-016-0140-9 (in Russian).

3. Klyuchnikov A. A., Sharaevsky I. G., Fialko N. M. et al. Thermophysics of Nuclear Reactor Accidents. Chernobyl, Institute of Nuclear Power Plant Safety Problems, 2012. 528 p. (in Russian).

4. Menter F. R., Kuntz M., Langtry R. Ten years of industrial experience with the SST turbulence model. Hanjalic K., Nagano Y., Tummers M., eds. Turbulence, Heat and Mass Transfer. 4th ed. New York, Begell House, Inc., 2003. P. 625–632.

5. Igarashi M., Tanaka M., Kawashima S. Experimental study on fluid mixing for evaluation of thermal striping in T-pipe junction. 10th International Conference on Nuclear Engineering: Proceesing, April 14–18, 2002. Arlington, USA, 2002. P. 383–390.