本文選題：核電 + 圖形化建模　； 參考：《東南大學(xué)》2015年碩士論文

【摘要】：近年來(lái)環(huán)境問(wèn)題日益突出,核電作為一種清潔能源,發(fā)展核電在優(yōu)化能源結(jié)構(gòu)及改善環(huán)境方面有著十分重要的意義。核電伴隨著其安全性的改善已經(jīng)發(fā)展到第三代,我國(guó)引進(jìn)第三代核電AP1000技術(shù),并自主研發(fā)CAP1400技術(shù)。計(jì)算機(jī)技術(shù)的快速發(fā)展使得仿真在工程領(lǐng)域的應(yīng)用日益增多,通過(guò)仿真軟件的驗(yàn)證與確認(rèn),減少了工程的研發(fā)成本并提高了工程的安全性。通過(guò)仿真軟件對(duì)核電站系統(tǒng)進(jìn)行建模仿真,提高電站的安全運(yùn)行系數(shù)。圖形化建模是當(dāng)前建模仿真行業(yè)的發(fā)展趨勢(shì),針對(duì)核電站本文開(kāi)發(fā)了一套圖形化建模仿真軟件虛擬電站。本文在分析國(guó)內(nèi)外核電仿真軟件的基礎(chǔ)上,采用圖形化和模塊化的理念開(kāi)發(fā)核電站建模仿真軟件。使用Visio作為圖形引擎,利用Visio Automation技術(shù)作為依托開(kāi)發(fā)圖形化建模平臺(tái)虛擬電站。設(shè)備數(shù)學(xué)模型采用模塊化建模,使用ActiveX技術(shù)進(jìn)行設(shè)備模塊封裝,具有良好的獨(dú)立性和可擴(kuò)展性。虛擬電站采用建立流體網(wǎng)絡(luò)的方式進(jìn)行熱力系統(tǒng)建模,軟件能夠自動(dòng)進(jìn)行系統(tǒng)組態(tài)圖的網(wǎng)絡(luò)拓?fù)浣Y(jié)構(gòu)分析并建立相應(yīng)的流體網(wǎng)絡(luò)模型,虛擬電站將流體網(wǎng)絡(luò)與設(shè)備模塊相結(jié)合,對(duì)熱力系統(tǒng)組態(tài)圖建立數(shù)學(xué)模型,實(shí)現(xiàn)熱力系統(tǒng)的實(shí)時(shí)仿真。針對(duì)儀控系統(tǒng),虛擬電站能夠?qū)崟r(shí)運(yùn)行控制邏輯組態(tài)圖。同時(shí),虛擬電站平臺(tái)中使用MySQL作為數(shù)據(jù)庫(kù),利用數(shù)據(jù)庫(kù)將熱力模型與儀控系統(tǒng)相結(jié)合,實(shí)現(xiàn)了系統(tǒng)建模仿真。本文對(duì)我國(guó)自主化第三代核電技術(shù)CAP1400的核島、常規(guī)島內(nèi)主要熱力系統(tǒng)和儀控系統(tǒng)進(jìn)行分析研究,并著重分析了主給水系統(tǒng)及反應(yīng)堆冷卻劑系統(tǒng)的工藝流程、設(shè)備配置和控制邏輯。本文采用機(jī)理推導(dǎo)和經(jīng)驗(yàn)歸納相結(jié)合的方式,建立了加熱器、泵、閥門(mén)、除氧器、反應(yīng)堆、蒸汽發(fā)生器等設(shè)備的數(shù)學(xué)模型,并制作了模具庫(kù)。使用虛擬電站進(jìn)行了設(shè)備模塊測(cè)試驗(yàn)證,結(jié)果表明模型設(shè)計(jì)正確,動(dòng)態(tài)趨勢(shì)合理,驗(yàn)證了模型的正確性。對(duì)主給水系統(tǒng)及反應(yīng)堆冷卻劑系統(tǒng)進(jìn)行系統(tǒng)建模仿真,運(yùn)行虛擬電站做調(diào)試實(shí)驗(yàn),對(duì)主給水系統(tǒng)及反應(yīng)堆冷卻劑系統(tǒng)進(jìn)行了系統(tǒng)驗(yàn)證。結(jié)果表明虛擬電站建立系統(tǒng)模型正確、功能實(shí)用,具有一定的工程應(yīng)用價(jià)值。
[Abstract]:In recent years, environmental problems have become increasingly prominent, nuclear power as a clean energy, the development of nuclear power in the optimization of energy structure and improve the environment has a very important significance.Nuclear power has been developed to the third generation with the improvement of its safety. China has introduced the third generation nuclear power AP1000 technology and independently developed CAP1400 technology.With the rapid development of computer technology, the application of simulation in engineering field is increasing day by day. Through the verification and confirmation of simulation software, the cost of engineering research and development is reduced and the safety of engineering is improved.The simulation software is used to model and simulate the nuclear power plant system to improve the safe operation coefficient of the power station.Graphical modeling is the development trend of modeling and simulation industry at present. A set of graphical modeling and simulation software virtual power station is developed in this paper.Based on the analysis of nuclear power simulation software at home and abroad, the modeling and simulation software of nuclear power plant is developed by using graphical and modular concept.Visio is used as graphics engine and Visio Automation technology is used to develop virtual power station based on graphical modeling platform.The mathematical model of equipment is modeled by modularization and encapsulated by ActiveX technology. It has good independence and expansibility.The virtual power station uses the method of establishing fluid network to model the thermodynamic system. The software can automatically analyze the network topology of the system configuration diagram and establish the corresponding fluid network model. The virtual power station combines the fluid network with the equipment module.The mathematical model of configuration diagram of thermal system is established, and the real-time simulation of thermal system is realized.For the instrument control system, the virtual power station can run the control logic configuration diagram in real time.At the same time, MySQL is used as the database in the virtual power station platform, and the thermal model is combined with the instrument control system to realize the system modeling and simulation.In this paper, the nuclear island of CAP1400, the main thermodynamic system and the instrument control system in the CAP1400 are analyzed and studied, and the technological process of the main feed water system and reactor coolant system are emphatically analyzed.Device configuration and control logic.In this paper, the mathematical models of heater, pump, valve, deaerator, reactor and steam generator are established by combining mechanism derivation and experience induction, and the mould library is made.The virtual power station is used to test and verify the equipment module. The results show that the model design is correct, the dynamic trend is reasonable, and the correctness of the model is verified.System modeling and simulation of main feed water system and reactor coolant system are carried out, debugging experiments of running virtual power station are carried out, and system verification of main feed water system and reactor coolant system is carried out.The results show that the system model of virtual power station is correct, the function is practical, and it has certain engineering application value.
【學(xué)位授予單位】：東南大學(xué)
【學(xué)位級(jí)別】：碩士
【學(xué)位授予年份】：2015
【分類(lèi)號(hào)】：TM623

【相似文獻(xiàn)】

相關(guān)期刊論文 前10條

1 王萍;;核電站常規(guī)島主給水系統(tǒng)瞬態(tài)計(jì)算概述[J];中國(guó)電業(yè)(技術(shù)版);2013年02期

2 陳睿;;有關(guān)核電廠(chǎng)主給水系統(tǒng)設(shè)計(jì)的探討[J];核安全;2005年02期

3 王曉東;黃濤;;CPR1000核電站主給水系統(tǒng)穩(wěn)態(tài)及瞬態(tài)工況分析[J];吉林電力;2014年02期

4 龔淵;;淺論秦山核電廠(chǎng)事故后恢復(fù)主給水運(yùn)行降低堆熔頻率[J];核安全;2006年01期

5 萬(wàn)偉;董慕杰;劉瑋;肖長(zhǎng)歌;;基于Petri網(wǎng)理論的核電站主給水系統(tǒng)建模及其可靠性分析[J];熱力發(fā)電;2013年12期

6 劉豐;達(dá)拉特電廠(chǎng)一期工程主給水系統(tǒng)設(shè)計(jì)方案選擇[J];內(nèi)蒙古電力;1992年04期

7 趙付濤,徐義亨,杜維;核電廠(chǎng)主給水系統(tǒng)PLC控制[J];化工自動(dòng)化及儀表;1998年03期

8 滿(mǎn)若巖;孔凡卓;許德忠;趙亮;林沖;;CPR與EPR型核電站主給水系統(tǒng)及設(shè)備對(duì)比研究[J];華東電力;2013年02期

9 魏明,萬(wàn)勝軍,王澤清;改進(jìn)鍋爐主給水系統(tǒng)調(diào)節(jié)閥的設(shè)計(jì)原則與方法[J];鍋爐制造;2001年02期

10 陳瑞克;;超超臨界機(jī)組汽水系統(tǒng)的設(shè)計(jì)特點(diǎn)分析[J];華電技術(shù);2008年02期

相關(guān)碩士學(xué)位論文 前2條

1 董慕杰;核電站主給水系統(tǒng)建模仿真及故障診斷[D];華北電力大學(xué);2015年

2 楊濤;核電站系統(tǒng)圖形化建模仿真及驗(yàn)證[D];東南大學(xué);2015年

，

本文編號(hào)：1738146