Method for establishing blocking condition models of heat transfer tubes of vapor generators in nuclear power plants

Abstract

The invention discloses a method for rapidly establishing three-dimensional fine thermos-hydraulic calculation models for primary side systems of large-scale natural circulation vapor generators in nuclear power plants under certain heat transfer tube blocking accident conditions. The method comprises the following steps of: 1, carrying out complete primary side hydraulic analysis on a vapor generator so as to analyze a flow distribution law at a tube plate; 2, selecting a tube blocking scheme according to a result of the last step; 3, determining a tube blocking share and a tube blocking position; 4, carrying out geometric simplification and overall geometric modeling on a plurality of heat transfer tubes in the real vapor generator; 5, dividing preliminary calculation nodes; 6, establishing a tube blocking equation to tracing marked control areas, and carrying out calculation domain grid marking on the control areas by adoption of a network marking method so as to realize a tube blocking function; and 7, carrying out blocking condition calculation by adoption of a preliminarily established model and analyzing the precision of the result, and if a requirement is satisfied, considering that the modeling is completed, and otherwise, returning to the step 5 to encrypt the calculation nodes until the model satisfies the calculation precision requirement.

Description

technical field [0001] The invention belongs to the technical field of heat transfer tubes of steam generators in nuclear power plants, and in particular relates to a method for establishing a model for the blocked flow condition of the heat transfer tubes of steam generators in nuclear power plants. Background technique [0002] U-shaped tube natural circulation steam generator ( figure 1 ) is a large-scale and important heat exchange equipment in the reactor system of a nuclear power plant, which plays an important role in the energy exchange between the primary circuit and the secondary circuit in the reactor system to derive the energy of the reactor core. Its large number of heat transfer tubes is the weakest pressure boundary of the primary circuit of a nuclear power plant. The thickness of the tube wall is only about 1 mm, showing the characteristics of high and long. There are high-temperature, high-pressure, highly corrosive, and high-speed vibrating fluids distrib...

AI Technical Summary

Problems solved by technology

In the process of pipe plugging, the economic loss of shutdown maintenance is quite large except for the maintenance cost, and the cost of replacing the steam generator is even higher. Therefore, the economic loss caused by the rupture of the heat transfer tube of the steam generator is quite large for the nuclear power system.

Images