Numerical study of convective heat transfer between core and steam generator in severe accident with loss of heat removal to secondary side of VVER reactors

The article discusses the possibility of overheating and failure of heat exchanging tubes in VVER steam generators in the course of severe accidents. The importance of this phenomenon is due to the risk of bypassing the containment by radioactive substances. Natural convection of superheated steam in the hot leg of the main circulation loop is considered as the major mechanism for heat transfer from the core to steam generators. To model convective flows and steam temperature distribution in a system, three-dimensional CFD codes are used. The simulation results demonstrate that the intensity of convective heat transfer from reactor to hot collector of steam generator is insufficient for significant heating and catastrophic degradation of strength of the heat exchange tubes material.

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Publication Details

Journal
Известия Российской академии наук Энергетика
Published
2024-12-21
DOI
https://doi.org/10.31857/s0002331024040063
Primary Topic
Nuclear Materials and Properties
Type
article
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article

Numerical study of convective heat transfer between core and steam generator in severe accident with loss of heat removal to secondary side of VVER reactors

A. A. Krutikov, A. V. Nikolaeva, K. S. Dolganov
Известия Российской академии наук Энергетика
Nuclear Materials and Properties
article

Numerical study of convective heat transfer between core and steam generator in severe accident with loss of heat removal to secondary side of VVER reactors

A. A. Krutikov, A. V. Nikolaeva, K. S. Dolganov
article en

Abstract

The article discusses the possibility of overheating and failure of heat exchanging tubes in VVER steam generators in the course of severe accidents. The importance of this phenomenon is due to the risk of bypassing the containment by radioactive substances. Natural convection of superheated steam in the hot leg of the main circulation loop is considered as the major mechanism for heat transfer from the core to steam generators. To model convective flows and steam temperature distribution in a system, three-dimensional CFD codes are used. The simulation results demonstrate that the intensity of convective heat transfer from reactor to hot collector of steam generator is insufficient for significant heating and catastrophic degradation of strength of the heat exchange tubes material.

Известия Российской академии наук Энергетика(4)
Russian Academy of Sciences (RU), Gidropribor (RU), Nuclear Safety Institute (RU)
Clean water and sanitation
Openalex Percentile: Top 85%
Nuclear Materials and Properties
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