Method for estimating primary and secondary side convective heat transfer coefficient distribution of steam generator

Abstract

The invention provides a method for estimating primary and secondary side convective heat transfer coefficient distribution of a steam generator. The method specifically comprises the following steps:acquiring real-time operation data of the steam generator at a given moment; establishing a descending channel model to obtain the flow, temperature and pressure of the liquid-phase working medium atthe bottom outlet of the descending channel at the current moment; establishing a primary loop coolant model, and obtaining the flow velocity, temperature and pressure distribution and primary side convective heat transfer coefficient distribution of a primary loop coolant along the height of the inverted-U-shaped pipe at the current moment; establishing an ascending channel model, and obtainingthe flow velocity, temperature and pressure distribution and secondary side convective heat transfer coefficient distribution of a secondary loop working medium along the height of the inverted-U-shaped pipe at the current moment; and establishing a steam-water separator model, and calculating to obtain the temperature, pressure and mass flow of a gas-phase working medium and a liquid-phase working medium at the outlet of the steam-water separator. According to the invention, real-time estimation of primary and secondary side convective heat transfer coefficient distribution of the steam generator can be realized.

Description

technical field [0001] The invention provides a real-time estimation (identification) method for the distribution of convective heat transfer coefficients of nuclear power steam generators combined with mechanism modeling and DCS (on-site distributed control system of operating units) real-time measurement data, belonging to the technical field of nuclear power plant operation optimization control . Background technique [0002] In a nuclear power plant, the high-temperature and high-pressure coolant from the reactor first enters the inlet of the steam generator, then flows into the inverted U-shaped tube, transfers the heat to the secondary side fluid through the metal tube wall of the inverted U-shaped tube, and then flows out of the U-shaped tube. out of the mouth. On the secondary side, the feed water is mixed with the recirculation fluid separated from the primary and secondary steam-water separators to form mixed water, which flows into the descending channel of the s...

AI Technical Summary

Problems solved by technology

The main contribution of this patent is to propose a steady-state mathematical model for homogeneous flow of steam generators, but it cannot dynamically output the distribution of convective heat transfer coefficients of the steam generator along the height of the inverted U-shaped tube and the primary and secondary sides in real time.

[0005] In summary, none of the existing public reports involve the real-time estimation of the distribution of convective heat transfer coefficients along the height of the inverted U-shaped tube of the nuclear power steam generator and the primary and secondary sides. This gap needs to be filled.

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