具導(dǎo)熱時滯的核反應(yīng)堆模型的Hopf分支
發(fā)布時間:2018-05-01 09:40
本文選題:核反應(yīng)堆 + 時滯�。� 參考:《哈爾濱工業(yè)大學(xué)》2015年碩士論文
【摘要】:核電作為一種高效、環(huán)保能源,可大幅減少空氣污染、促進我國能源獨立。核電產(chǎn)業(yè)的發(fā)展離不開核安全問題,核反應(yīng)堆運行務(wù)必要保障反應(yīng)堆堆芯的安全性,核電控制系統(tǒng)可擔(dān)此任。該系統(tǒng)主要通過測量冷卻劑平均溫度,控制反應(yīng)堆功率來保證核電站正常運轉(zhuǎn)。因此,溫度與功率是研究核反應(yīng)堆運行安全的兩個關(guān)鍵變量。本文對Kostas Bucys建立的具時滯的二維點堆模型進行了動力學(xué)性質(zhì)分析。這里引入時滯,即冷卻劑通過管道所需要的時間來刻畫核電站控制系統(tǒng)對堆內(nèi)溫度的測量控制。首先,考慮了時滯?對系統(tǒng)平衡點穩(wěn)定性的影響,并得到了在正平衡點處存在局部Hopf分支的充分條件。在Hassard等人提出的中心流形約化方法和規(guī)范型理論的基礎(chǔ)上,研究了正平衡點處的Hopf分支方向和分支周期解穩(wěn)定性,并推導(dǎo)了顯示公式。其次,利用吳建宏等人建立的全局Hopf分支理論研究了分支周期解的大范圍存在性。通過這些理論分析,我們得到了冷卻劑通過管道所需的時間的長短(即時滯的大小)對反應(yīng)堆堆芯安全的影響。當(dāng)時滯的大小在一定范圍內(nèi),并且模型中的相關(guān)參數(shù)滿足一定條件時,反應(yīng)堆的溫度和功率都將被限制在一個區(qū)間內(nèi)。最后,使用MATLAB軟件進行數(shù)值模擬,得到了當(dāng)參數(shù)滿足一定條件時確實可以防止反應(yīng)堆的功率和溫度升高到不可接受的程度,因此數(shù)值模擬結(jié)果例證了理論分析結(jié)果的正確性。
[Abstract]:Nuclear power, as an efficient and environmentally-friendly energy, can greatly reduce air pollution and promote energy independence in China. The development of nuclear power industry can not do without nuclear safety, nuclear reactor operation must ensure the safety of reactor core, nuclear power control system can assume this role. The system ensures the normal operation of the nuclear power plant by measuring the coolant average temperature and controlling the reactor power. Therefore, temperature and power are two key variables to study the safety of nuclear reactor operation. In this paper, the dynamical properties of a two dimensional point heap model with time delay established by Kostas Bucys are analyzed. Time delay is introduced to describe the measurement and control of the temperature in the reactor by the control system of the nuclear power plant in terms of the time required for the coolant to pass through the pipeline. First, time delay is considered? The sufficient conditions for the existence of local Hopf bifurcation at the positive equilibrium point are obtained. Based on the center manifold reduction method and normal form theory proposed by Hassard et al, the direction of Hopf bifurcation and the stability of bifurcation periodic solution at positive equilibrium point are studied, and the display formula is derived. Secondly, using the global Hopf bifurcation theory established by Wu Jian-hong and others, we study the existence of the periodic solutions in a large range. Based on these theoretical analyses, we have obtained the influence of the length of time required for the coolant to pass through the pipeline (i.e., the size of the time lag) on the reactor core safety. When the hysteresis is within a certain range and the parameters in the model satisfy certain conditions, the temperature and power of the reactor will be confined to a certain range. Finally, the numerical simulation with MATLAB software shows that the power and temperature of the reactor can be prevented from rising to an unacceptable level when the parameters meet certain conditions, so the numerical simulation results illustrate the correctness of the theoretical analysis results.
【學(xué)位授予單位】:哈爾濱工業(yè)大學(xué)
【學(xué)位級別】:碩士
【學(xué)位授予年份】:2015
【分類號】:O175
【參考文獻】
相關(guān)期刊論文 前1條
1 何鴻;張壽庭;韋龍明;徐毅;;核電發(fā)展形勢與對策建議[J];資源與產(chǎn)業(yè);2010年04期
,本文編號:1828813
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