Assessment of the influence of the crisis flow of a swirling flow on the thermohydraulic efficiency of shipboard nuclear power installations


Аuthors

Mitrofanova O. V.1, 2*, Ivlev O. A.1, Urtenov D. S.1**, Fedorinov A. V.1, 2

1. ,
2. National Research Nuclear University MEPhI (Moscow Engineering Physics Institute), 31, Kashirskoe shosse, Moscow, 115409, Russia

*e-mail: omitr@yandex.ru
**e-mail: urtenov_ds@nrcki.ru

Abstract

The specific differences between ship nuclear power installations and ground-based nuclear power plants with water-water reactors (VVER type) are considered. The directions of scientific research relevant to the substantiation of optimal design solutions to improve the efficiency and reliability of the ship’s nuclear power installations of the new generation are determined. Computational and theoretical studies on modeling of hydrodynamics and heat transfer processes in the channels of the thermal-hydraulic tract of the ship’s steam-producing installation are carried out. It is shown that the complex geometry of the curvilinear channels of the thermal-hydraulic path of the steam generating system has a significant impact on the efficiency of the transport nuclear power installation.

The scientific and applied significance of the proposed research is associated with the need to provide a wide range of operational changes in the power modes of the effective and safe operation of icebreaking nuclear power installations. The present research aimed at developing the principles of physical and mathematical modeling of complex vortex flows is necessary to optimize the constructive parameters of the elements of thermal power equipment of ship nuclear power installations of the new generation in order to ensure increased safety and reliability of their operation.

Keywords:

vortex flow, steam generating unit, heat and energy efficiency, chirality, vortici-ty, spiral-helix flow

References

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