A system and method for evaluating thermal performance of a vertical steam generator

Abstract

The present invention provides a thermal performance evaluation system and method of a vertical steam generator, which includes dividing a plurality of different regions according to the single or two-phase characteristics of the tube side and shell side structure of the steam generator and fluid flow to establish their corresponding entropy production calculations The thermal hydraulic modeling module of the model; the detection module for detecting the temperature, pressure and flow signals corresponding to the tube side and the shell side during the operation of the steam generator; according to the processed temperature, pressure and flow signals, and call the corresponding entropy The production calculation model calculates the corresponding entropy production according to the tube side and the shell side respectively, and calculates the total entropy production of the heat exchange system of the steam generator, which is a calculation and analysis module for overall evaluation of the thermal performance of the steam generator; the present invention simultaneously Considering the irreversible entropy production on the tube side and the shell side, it covers all areas of the steam generator and fully feeds back the whole heat transfer process of the steam generator; it provides a valuable reference for the design and thermodynamic analysis of the steam generator.

Description

technical field [0001] The invention relates to the technical field of nuclear power plants, in particular to a thermal performance evaluation system and method for a vertical U-shaped natural steam generator of a nuclear power plant. Background technique [0002] Entropy is one of the parameters of the standard state of matter in thermodynamics, and its physical meaning is the degree of disorder of the system. In a nuclear power plant, besides the reactor, the most important equipment is the steam generator, which takes the energy generated by nuclear fission of the core out of the primary circuit coolant, transfers the heat to the feed water of the secondary circuit, and generates steam with a certain pressure and temperature. The steam is sent to the steam turbine to do work, which is the hub connecting the reactor and the steam turbine, so the working state of the steam generator affects the dynamic characteristics of the entire PWR equipment. [0003] The steam generat...

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Problems solved by technology

[0005] The present invention aims at the technical problems existing in the prior art that the deviation of the analysis result is relatively large, the analysis area is incomplete, and the entire working process of the heat exchange of the steam generator cannot be effectively covered. Vertical steam generator thermal performance evaluation system and evaluation method for establishing a complete analysis and evaluation system

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