發(fā)布時間：2018-03-13 20:25

  本文選題：鈉冷快堆　切入點：系統(tǒng)分析軟件　出處：《華北電力大學(xué)》2013年碩士論文　論文類型：學(xué)位論文

【摘要】：隨著全球化經(jīng)濟的迅速發(fā)展,化石能源的加速消耗及其帶來的環(huán)境問題日益加劇,核能以其安全、經(jīng)濟、高效且可短期內(nèi)大規(guī)模利用并替代傳統(tǒng)化石能源的優(yōu)勢,在世界范圍內(nèi)廣泛被利用。鈉冷快堆是我國核能發(fā)展“三步走”戰(zhàn)略中的第二步,能夠解決目前壓水堆發(fā)展中存在的鈾資源利用率低和長壽命高放廢物對環(huán)境威脅問題,可進(jìn)一步提升核電在清潔能源中的競爭力。 堵流導(dǎo)致鈉沸騰問題是堆芯熔化事故的起始序列之一,也是鈉冷快堆設(shè)計及其安全分析工作中必須要考慮的一個問題。本文主要任務(wù)是在鈉冷快堆系統(tǒng)分析軟件中,開發(fā)堆芯冷卻劑通道堵流導(dǎo)致的鈉沸騰模型,以填補我國鈉冷快堆系統(tǒng)分析軟件中沒有鈉沸騰模型的不足。 程序計算結(jié)果表明：首先由于鈉冷卻劑氣液兩相密度差達(dá)數(shù)千倍乃至萬倍,因而在入口冷卻劑流量逐漸減少,其溫度逐漸上升,達(dá)到沸騰的瞬間,少量相變就會引起通道內(nèi)出現(xiàn)較大的空泡份額；其次由于鈉冷卻劑為液態(tài)金屬冷卻劑,其導(dǎo)熱特性優(yōu)良,包殼和冷卻劑溫差較小,只有幾K左右,因而冷卻劑通道內(nèi)沸騰起始位置一般發(fā)生冷卻劑通道出口處,隨著入口流量的減少,該位置逐漸降低。文章最后運用商用CFD軟件對程序計算結(jié)果進(jìn)行對比驗證,兩者結(jié)果十分吻合,表明模型開發(fā)的合理性。
[Abstract]:With the rapid development of global economy, the accelerated consumption of fossil energy and its environmental problems are becoming more and more serious. Nuclear energy has the advantages of safety, economy, efficiency and short-term large-scale utilization and replacement of traditional fossil energy. Sodium cold fast reactor is the second step in the "three step" strategy of nuclear energy development in China, which can solve the problem of low utilization of uranium resource and long life high radioactive waste in the development of pressurized water reactor (PWR). It can further enhance the competitiveness of nuclear power in clean energy. The problem of sodium boiling caused by blocking flow is one of the starting sequences of core melting accident, and it is also a problem that must be considered in the design and safety analysis of sodium cooled fast reactor. The main task of this paper is in the system analysis software of sodium cooled fast reactor. The sodium boiling model caused by core coolant channel blockage is developed to fill the shortage of sodium boiling model in the system analysis software of sodium cooled fast reactor in China. The program results show that, first of all, because the density difference of gas-liquid two-phase of sodium coolant reaches several thousand or ten thousand times, the flow rate of the inlet coolant decreases gradually, and the temperature rises gradually, reaching the moment of boiling. A small amount of phase change will lead to a large amount of cavitation in the channel. Secondly, because the sodium coolant is a liquid metal coolant, its thermal conductivity is good, and the temperature difference between the cladding and the coolant is small, which is only a few K or so. Therefore, the starting position of boiling in the coolant channel generally occurs at the outlet of the coolant channel. With the decrease of the inlet flow rate, the position decreases gradually. Finally, commercial CFD software is used to verify the calculation results of the program. The results are in good agreement with each other, which indicates the rationality of the model development.
【學(xué)位授予單位】：華北電力大學(xué)
【學(xué)位級別】：碩士
【學(xué)位授予年份】：2013
【分類號】：TL364.4

【參考文獻(xiàn)】

相關(guān)期刊論文 前10條

1 武宏波;王智冬;項冰;;國內(nèi)外核電發(fā)展形勢分析[J];能源技術(shù)經(jīng)濟;2012年03期

2 李志印,熊小輝,吳家鳴;計算流體力學(xué)常用數(shù)值方法簡介[J];廣東造船;2004年03期

3 石曉波;羅銳;王洲;;快堆單個燃料組件完全堵流事故的建模及其驗證[J];核動力工程;2006年01期

4 趙樹峰;羅銳;王洲;石曉波;楊獻(xiàn)勇;;快堆沸騰池數(shù)學(xué)模型[J];核動力工程;2007年04期

5 張東輝,王 洲,徐 钅米;利用子通道程序?qū)於讯研径铝鞯挠嬎鉡J];核科學(xué)與工程;1999年04期

6 石曉波,羅銳,王洲,楊獻(xiàn)勇;鈉冷快堆單個燃料組件冷卻劑沸騰的數(shù)值模擬[J];核科學(xué)與工程;2004年04期

7 秋穗正,張維忠,廖義香,賈斗南;液鈉沸騰兩相流流型與臨界熱流密度(CHF)機理實驗研究[J];核科學(xué)與工程;2001年03期

8 邱仁森;快堆燃料組件局部堵流實驗研究工作[J];核動力工程;1982年04期

9 魯嘉華;計算流體力學(xué)與求解方法在葉輪機械中的應(yīng)用[J];上海工程技術(shù)大學(xué)學(xué)報;2003年01期

10 孫德意;宋浩亮;許俊斌;;從世界核電站發(fā)展趨勢看我國核電發(fā)展現(xiàn)狀[J];上海電氣技術(shù);2011年02期

相關(guān)碩士學(xué)位論文 前2條

1 王雪飛;基于虛擬儀器技術(shù)的中國實驗快堆可視化仿真系統(tǒng)的開發(fā)與研究[D];中國原子能科學(xué)研究院;2007年

2 楊林民;超臨界水冷堆主容器出口管的設(shè)計研究[D];華北電力大學(xué)（北京）;2008年

，

本文編號：1608023