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Study On The Simulation Model And Dynamic Characteristics Of Primary Coolant System Fluid Network Of PWR

Posted on:2013-08-16Degree:MasterType:Thesis
Country:ChinaCandidate:X L LiuFull Text:PDF
GTID:2232330395476508Subject:Thermal Engineering
Abstract/Summary:PDF Full Text Request
Nuclear energy power generation as a developed utilization method of new energy, it is pollution-free and economical efficiency. At present the fossil energy less and less, nuclear power fast development in the world. Because of the particularity of nuclear power units, its safety is given more attention. Nuclear power units simulator can improve the operation level of the operating personnel and has profound implications to the safety of nuclear energy power generation.The simulation program of nuclear power units Coolant system involves two-phase flow. The two-phase flow network model was built using the method of modularization on the platform of IMMS. IMMS is an integrated simulation software, it has the advantages of modeling efficiency and small amount of maintenance. The foundation of the model is drift flow model. The main characteristic of drift flow model is considering the relative slipping speed. The model mainly consists of node algorithm and link algorithm. Quality, energy and momentum conservation and other basic equations and some experience formula as algorithms’the theory basis.This paper established a two-phase flow network model, it is suit for the simulation of two-phase flow networks of various of topological structures and can also be used in the simulation of a single-phase fluid network. Several dynamic simulation experiments have been made in order to study the dynamic running characteristic of the system under different varying duties. Draw the dynamic response characteristics curve of two-phase flow, and compared the result of drift flow model and homogenous two-phase flow model. Analyzes the effect of pressure, void fraction and pipeline gradient to drift flow model, and it offers a kind of important technical means for the two-phase flow research. The reliability and practical meaning could be evidenced by the compliance of the experiment of the results with the reported references. Therefore, it can provide several reasonable advices and theoretical basis to the unit operation and control.
Keywords/Search Tags:PWR, coolant system, two-phase flow, mathematical model, simulation
PDF Full Text Request
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