A method for estimating the distribution of convective heat transfer coefficients on the primary and secondary sides of a steam generator

Abstract

The invention provides a method for estimating the distribution of convective heat transfer coefficients on the primary and secondary sides of a steam generator, which specifically includes: obtaining real-time operating data of the steam generator at a given moment; establishing a descending channel model, and obtaining the outlet at the bottom of the descending channel at the current moment The flow rate, temperature and pressure of the liquid-phase working medium; establish a primary circuit coolant model, and obtain the flow velocity, temperature, pressure distribution and primary side convective heat transfer coefficient distribution of the primary circuit coolant along the height of the inverted U-shaped tube at the current moment; establish an ascent Channel model, to obtain the flow velocity, temperature, pressure distribution of the secondary circuit working fluid along the height of the inverted U-shaped tube at the current moment, and the distribution of the secondary side convective heat transfer coefficient; establish a steam-water separator model, and calculate the gas-phase working fluid at the outlet of the steam-water separator, The temperature, pressure and mass flow rate of liquid phase working fluid. The invention can realize the real-time estimation of the distribution of convective heat transfer coefficient on the primary and secondary sides of the steam generator.

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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