本文選題：內(nèi)陸核電站　切入點(diǎn)：自然循環(huán)逆流濕式冷卻塔　出處：《哈爾濱工程大學(xué)》2014年碩士論文　論文類(lèi)型：學(xué)位論文

【摘要】：與沿海核電站循環(huán)冷卻系統(tǒng)采用的開(kāi)式循環(huán)方式不同,內(nèi)陸核電站循環(huán)冷卻系統(tǒng)基本采用冷卻塔閉式循環(huán)冷卻方式,環(huán)境大氣是散熱的最終熱阱。冷卻塔的傳熱傳質(zhì)動(dòng)態(tài)響應(yīng)將影響冷凝器入口冷卻水水溫,進(jìn)而對(duì)核電站的效率及安全造成影響。目前對(duì)冷卻塔的分析計(jì)算基本針對(duì)穩(wěn)態(tài)工況,通過(guò)分析其結(jié)構(gòu)與設(shè)計(jì)性能的關(guān)系來(lái)優(yōu)化設(shè)計(jì),用于運(yùn)行特性分析的實(shí)時(shí)動(dòng)態(tài)仿真計(jì)算研究未見(jiàn)報(bào)道。對(duì)冷卻塔的瞬態(tài)進(jìn)行仿真模擬,可研究?jī)?nèi)陸核電站事故工況下的安全性,因此其具有重大的工程與理論意義。本文以自然循環(huán)逆流濕式冷卻塔為研究對(duì)象,通過(guò)詳細(xì)分析冷卻塔內(nèi)傳熱傳質(zhì)和流動(dòng)過(guò)程,研究建立了描述冷卻塔內(nèi)空氣和循環(huán)水流動(dòng)的動(dòng)態(tài)數(shù)學(xué)物理模型,以及以Merkel模型為基礎(chǔ)的氣、水間傳熱傳質(zhì)模型。假設(shè)氣流場(chǎng)為二維軸對(duì)稱不可壓縮流動(dòng),采用有限體積法及SIMPLE算法來(lái)求解二維的Navier-Stonkes方程,假設(shè)水流場(chǎng)為一維流動(dòng),采用經(jīng)典的四階Runge-Kutta法求解一維的常微分方程。采用Fortran語(yǔ)言完成仿真程序的編寫(xiě)及調(diào)試,并以某600MW電站的實(shí)際運(yùn)行參數(shù)進(jìn)行計(jì)算,將出塔水溫的計(jì)算值與實(shí)測(cè)值做了對(duì)比,驗(yàn)證模型和程序的正確性。在此基礎(chǔ)上,選取某氣象條件,分別針對(duì)淋水密度均勻分布及淋水密度沿徑向成線性分布的不同工況,對(duì)空氣場(chǎng)的速度、溫度以及含濕量的分布進(jìn)行了分析,并對(duì)水流場(chǎng)的水溫分布以及各特征面上的水溫分布進(jìn)行了分析,之后,分別考察了進(jìn)塔水溫、進(jìn)塔水流量、進(jìn)塔空氣相對(duì)濕度、進(jìn)塔氣溫這些參數(shù)的變化對(duì)出塔水溫的影響,最后計(jì)算了電站在變負(fù)荷或事故工況下,循環(huán)水入口溫度和流量發(fā)生改變時(shí),冷卻塔出口氣溫和水溫的瞬態(tài)響應(yīng)曲線,為內(nèi)陸核電站冷卻塔的設(shè)計(jì)和運(yùn)行提供了進(jìn)一步的依據(jù)。
[Abstract]:Different from the open circulation mode used in the circulating cooling system of the coastal nuclear power station, the circulating cooling system of the inland nuclear power station basically adopts the closed cycle cooling mode of the cooling tower. The ambient atmosphere is the final heat trap for heat dissipation. The dynamic response of heat and mass transfer of cooling tower will affect the temperature of cooling water at the inlet of condenser, and then affect the efficiency and safety of nuclear power station. At present, the analysis and calculation of cooling tower is basically aimed at the steady state condition. By analyzing the relationship between the structure and the design performance to optimize the design, the study of real-time dynamic simulation for the operation characteristic analysis has not been reported. The transient simulation of the cooling tower can be used to study the safety of the inland nuclear power plant under the accident condition. Therefore, it is of great engineering and theoretical significance. In this paper, the natural circulation countercurrent wet cooling tower is taken as the research object, and the heat and mass transfer and flow process in the cooling tower are analyzed in detail. A dynamic mathematical and physical model describing the flow of air and circulating water in a cooling tower and a model of heat and mass transfer between gas and water based on Merkel model are established. It is assumed that the flow field is two dimensional axisymmetric incompressible flow. The finite volume method and SIMPLE algorithm are used to solve the two-dimensional Navier-Stonkes equation. The water flow field is assumed to be a one-dimensional flow. The classical four-order Runge-Kutta method is used to solve the one-dimensional ordinary differential equation. The Fortran language is used to complete the programming and debugging of the simulation program. The actual operation parameters of a 600MW power station are calculated, and the calculated values of the water temperature of the outlet tower are compared with the measured values to verify the correctness of the model and the program. On this basis, a certain meteorological condition is selected. The velocity, temperature and moisture content distribution of air field are analyzed under different conditions of uniform distribution of water density and linear distribution of water density along radial direction. The water temperature distribution of the water flow field and the water temperature distribution on each characteristic surface are analyzed. After that, the effects of the water temperature of the inlet tower, the flow rate of the inlet tower, the relative humidity of the air in the inlet tower and the temperature of the inlet tower on the water temperature of the outlet tower are investigated respectively. Finally, the transient response curves of air temperature and water temperature at the outlet of cooling tower are calculated when the inlet temperature and flow rate of circulating water change under the condition of variable load or accident, which provides a further basis for the design and operation of cooling tower in inland nuclear power station.
【學(xué)位授予單位】：哈爾濱工程大學(xué)
【學(xué)位級(jí)別】：碩士
【學(xué)位授予年份】：2014
【分類(lèi)號(hào)】：TM623

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