本文選題：共軛梯度法 + 有限單元法�。� 參考：《北京化工大學(xué)》2017年博士論文

【摘要】：隨著社會(huì)經(jīng)濟(jì)的發(fā)展我國(guó)能源需求日益增長(zhǎng),核電作為一種高效清潔能源正蓬勃發(fā)展起來(lái),而核安全也成為人們關(guān)注的話題。在核電的諸多管道中,經(jīng)常會(huì)遇到冷熱流體匯合、熱分層等溫度波動(dòng)情況。管道內(nèi)溫度波動(dòng)可能誘發(fā)管道發(fā)生熱疲勞失效,導(dǎo)致核電管道發(fā)生泄漏。以波動(dòng)管熱分層為例,包括中國(guó)在內(nèi)的核電國(guó)家,無(wú)論是在役,還是擬建的核電站都必須完成波動(dòng)管熱分層分析與危害評(píng)估,足以看出熱分層誘發(fā)管道熱疲勞失效的重要性。由于結(jié)構(gòu)完備性要求,對(duì)于核電的管道系統(tǒng),不允許在管道內(nèi)部或者壁面開(kāi)孔來(lái)安裝熱電偶測(cè)量流體溫度和內(nèi)壁面溫度,這需要探索一種間接無(wú)損的溫度測(cè)量或評(píng)估方法來(lái)獲得管道內(nèi)流體和內(nèi)壁面溫度。本文提出瞬態(tài)多參量導(dǎo)熱反問(wèn)題(Transient Inverse Heat Conduction Problem with Multi-variables)來(lái)預(yù)測(cè)核電典型管道溫度波動(dòng)現(xiàn)象,亦即利用易于測(cè)量的管道外壁面溫度,通過(guò)共軛梯度法對(duì)圓管的近壁面流體溫度、內(nèi)壁面溫度及內(nèi)壁面對(duì)流換熱系數(shù)進(jìn)行反演,同時(shí)還可獲得整個(gè)管道的瞬時(shí)溫度場(chǎng)。本文主要在以下幾個(gè)方面開(kāi)展研究:(1)二維和三維圓管導(dǎo)熱正問(wèn)題與瞬態(tài)多參量導(dǎo)熱反問(wèn)題研究。構(gòu)建了基于有限元法的二維和三維圓管的導(dǎo)熱正問(wèn)題求解模型,進(jìn)行了網(wǎng)格無(wú)關(guān)性驗(yàn)證及時(shí)間步長(zhǎng)敏感性分析,為反問(wèn)題實(shí)驗(yàn)臺(tái)的測(cè)點(diǎn)布置方案及溫度采集頻率的確定提供了理論依據(jù)。構(gòu)建了基于共軛梯度法的瞬態(tài)多參量導(dǎo)熱反問(wèn)題模型,給出了利用外壁面測(cè)量溫度反演內(nèi)壁面第三類邊界條件的具體實(shí)施步驟。(2)瞬態(tài)多參量導(dǎo)熱反問(wèn)題實(shí)驗(yàn)校驗(yàn)及結(jié)果分析。搭建了基于熱分層原理的導(dǎo)熱反問(wèn)題實(shí)驗(yàn)臺(tái),進(jìn)行了導(dǎo)熱反問(wèn)題實(shí)驗(yàn)。研究利用實(shí)驗(yàn)結(jié)果對(duì)二維和三維導(dǎo)熱反問(wèn)題模型及反演結(jié)果進(jìn)行了校驗(yàn)�；谛ｒ�(yàn)過(guò)的導(dǎo)熱反問(wèn)題模型,研究了測(cè)點(diǎn)數(shù)對(duì)反演精度的影響,研究結(jié)果表明測(cè)點(diǎn)數(shù)越多,反演精度越高。當(dāng)二維導(dǎo)熱反問(wèn)題測(cè)點(diǎn)數(shù)降低到2個(gè)時(shí),平均相對(duì)誤差不超過(guò)4.3%,三維導(dǎo)熱反問(wèn)題測(cè)點(diǎn)數(shù)降低到6個(gè)時(shí),平均相對(duì)誤差不超過(guò)6.8%。從導(dǎo)熱反問(wèn)題實(shí)驗(yàn)結(jié)果及反演結(jié)果可以看出:管道內(nèi)壁各測(cè)點(diǎn)處的熱邊界層厚度隨冷水流量的增大呈現(xiàn)出不同的變化規(guī)律,多數(shù)測(cè)點(diǎn)處的熱邊界層厚度隨冷水流量的增大而變厚;反演的對(duì)流換熱系數(shù)值隨冷水流量的增大而略有增大;管壁的溫度分布規(guī)律也隨冷水流量的變化而發(fā)生明顯改變。(3)二維瞬態(tài)多參量導(dǎo)熱反問(wèn)題反演波動(dòng)管內(nèi)壁面第三類邊界條件。利用已校驗(yàn)的二維瞬態(tài)多參量導(dǎo)熱反問(wèn)題模型對(duì)核電穩(wěn)壓器波動(dòng)管4個(gè)沿管道軸線的易發(fā)生熱分層現(xiàn)象的典型截面進(jìn)行了反演。從計(jì)算結(jié)果中可以明顯看出截面所處位置的不同,其溫度場(chǎng)分布規(guī)律不同。24D和27D截面的壁面溫度最高點(diǎn)位于管道頂部,溫度最低點(diǎn)位于管道底部,而20D和22D管壁溫度最高點(diǎn)位置向右發(fā)生了偏移。這是由于管道的幾何特征致使流體流動(dòng)方向改變?cè)斐傻�。另�?四個(gè)截面得出的對(duì)流換熱系數(shù)也不盡相同,處于彎管處的截面,其對(duì)流換熱系數(shù)較大,但四個(gè)截面的對(duì)流換熱系數(shù)值相差不大,這也說(shuō)明了三維導(dǎo)熱反問(wèn)題中求解平均對(duì)流換熱系數(shù)的可行性。(4)熱分層三維彎管正問(wèn)題數(shù)值試驗(yàn)及反問(wèn)題結(jié)果分析。對(duì)存在熱分層現(xiàn)象的三維彎管進(jìn)行了瞬態(tài)導(dǎo)熱正問(wèn)題及多參量導(dǎo)熱反問(wèn)題研究,由抗噪性和外壁面測(cè)點(diǎn)數(shù)討論得知,存在一定的“測(cè)量”誤差時(shí),該方法仍可以得到一定精度的反演結(jié)果,彎管拐角區(qū)域的測(cè)點(diǎn)數(shù)對(duì)反演精度影響較大,該區(qū)域的測(cè)點(diǎn)數(shù)越多,反演精度越高,其他區(qū)域的測(cè)點(diǎn)數(shù)對(duì)反演精度的影響較小。(5)三維瞬態(tài)多參量導(dǎo)熱反問(wèn)題反演熱分層T型彎管溫度分布。利用已校驗(yàn)的三維瞬態(tài)多參量導(dǎo)熱反問(wèn)題模型對(duì)存在有熱分層的T型彎管的彎管段進(jìn)行了反演,揭示了在湍流穿透和浮升力作用下管壁及近壁面流體在不同時(shí)刻的溫度分布規(guī)律。本文所提出的一種多參量、無(wú)損、間接的溫度反演方法,利用外壁面的溫度信息同時(shí)求解管道內(nèi)壁第三類邊界條件的多個(gè)參量。經(jīng)實(shí)驗(yàn)校驗(yàn),此方法具有較高的精度。瞬態(tài)多參量導(dǎo)熱反問(wèn)題得到的結(jié)果不僅可為管道內(nèi)部流場(chǎng)的分析提供準(zhǔn)確的內(nèi)壁面邊界條件,而且可為管道的應(yīng)力分析提供準(zhǔn)確的瞬時(shí)熱載荷。對(duì)于核電等結(jié)構(gòu)完備性要求較高的管道系統(tǒng),此方法可以為其流場(chǎng)分析以及熱疲勞分析提供可靠的理論依據(jù)。
[Abstract]:With the development of social and economic development, nuclear power is developing vigorously as a kind of efficient clean energy, and nuclear safety has become a topic of concern. In many pipelines of nuclear power, there are often cold and hot fluid convergence, thermal stratification and other temperature fluctuations. The temperature fluctuation within the pipeline may induce pipelines to occur. Thermal fatigue failure causes leakage of nuclear power pipelines. Taking the thermal stratification of the wave tube as an example, the nuclear power countries including China, whether in service or in the proposed nuclear power plant, must complete the analysis of the thermal stratification and hazard assessment of the undulate tube, which is sufficient to see the importance of the thermal fatigue failure of the pipeline caused by thermal stratification. The pipeline system of nuclear power does not allow the internal or wall opening of the pipe to install the thermocouple to measure the temperature of the fluid and the inner wall temperature. This needs to explore an indirect and nondestructive temperature measurement or evaluation method to obtain the internal and internal temperature in the pipe. This paper proposes a transient multi parameter heat conduction inverse problem (Transient Inverse Heat Conducti). On Problem with Multi-variables) is used to predict the temperature fluctuation in the typical pipeline of nuclear power, that is to use the easily measured temperature of the outer wall of the pipe, the inversion of the near wall fluid temperature, the inner wall temperature and the inner wall facing the flow heat transfer coefficient by the conjugate gradient method, and the instantaneous temperature field of the whole pipe can be obtained at the same time. The following research should be carried out in the following aspects: (1) research on the positive and transient heat conduction problems of two-dimensional and three-dimensional tubes and transient multiparametric heat conduction problems. A finite element method for solving the positive problem of heat conduction in two-dimensional and three-dimensional tubes is constructed, and the grid independence verification and time step sensitivity analysis are carried out for the layout of the test point of the inverse problem test bench. A theoretical basis is provided for the determination of the frequency of temperature collection. A transient multi parameter heat conduction inverse problem model based on conjugate gradient method is constructed, and the concrete implementation steps for the inversion of third kinds of boundary conditions on the inner wall surface using the measuring temperature of the outer wall are given. (2) the test of the transient multi parameter heat conduction experiment and the result analysis. The experiment on the inverse heat conduction problem of the stratified principle is carried out. The experimental results are used to verify the inverse heat conduction problem model and the inverse result of the two-dimensional and three-dimensional heat conduction. Based on the checked heat conduction inverse problem model, the influence of the number of measured points on the inversion accuracy is studied. The results show that the number of points is more, the more accurate the inversion is. When the number of two dimensional heat conduction inverse problems is reduced to 2, the average relative error is not more than 4.3%, and the number of three dimensional heat conduction inverse problem points is reduced to 6. The average relative error is not more than 6.8%. from the experimental results of the heat conduction inverse problem and the inversion results can be seen that the thickness of the thermal boundary layer at the inner wall of the pipeline increases with the increase of the cold water flow. The thermal boundary layer thickness at most of the test points thickens with the increase of cold water flow. The numerical value of the inverse heat transfer system increases slightly with the increase of cold water flow, and the temperature distribution of the tube wall changes obviously with the change of the cold water flow. (3) the inversion of the two-dimensional transient multi parameter heat conduction inverse problem is in the wave tube. The third type boundary condition of the wall surface is used to inverse the typical cross section of the thermal delamination phenomenon of the nuclear power regulator's wave tube along the axis of the nuclear power regulator, using the checked two-dimensional transient multi parameter heat conduction inverse problem model. From the calculation results, it is obvious that the location of the section is different, and the distribution of temperature field is different.24D and 27D intercepts. The highest point of surface temperature is located at the top of the pipe, and the lowest temperature is located at the bottom of the pipe, while the position of the highest temperature of 20D and 22D is shifted to the right. This is caused by the change of the flow direction of the pipe because of the geometric characteristics of the pipe. In addition, the convection heat transfer coefficient of the four cross sections is not the same, at the bend of the pipe. The convective heat transfer coefficient is large, but the difference in the numerical value of the convective heat transfer system in the four cross sections is not significant. It also shows the feasibility of solving the average convection heat transfer coefficient in the three-dimensional heat conduction inverse problem. (4) the numerical test of the positive problem of the thermal stratified three-dimensional bend tube and the analysis of the inverse problem results. The problem and the inverse problem of multi parameter heat conduction are studied. From the discussion of the noise resistance and the number of exterior wall points, it is found that when there is a certain "measurement" error, the method can still get a certain precision of inversion results. The number of measuring points in the corner area has a great influence on the inversion accuracy, the more the number of the measured points in the region, the higher the inversion accuracy, the measurement of other regions. The number of points has little influence on the inversion accuracy. (5) the inversion of the thermal stratified T type pipe temperature distribution in the three-dimensional transient multi parameter heat conduction inverse problem. The inversion of the bend pipe section of the T type pipe with thermal stratification has been retrieved by using the checked three-dimensional transient multi parametric heat conduction inverse problem model, and the tube wall and the near wall surface under the effect of turbulent penetration and floating lift are revealed. The temperature distribution of fluid at different times. A multi parameter, nondestructive and indirect temperature inversion method proposed in this paper is used to use the temperature information of the outer wall to solve the multiple parameters of the third kinds of boundary conditions of the inner wall of the pipe. It is verified by experiments that the method has a high degree of precision. It can only provide accurate inner wall boundary conditions for the analysis of the internal flow field of the pipeline, and can provide accurate instantaneous thermal load for the stress analysis of the pipeline. This method can provide a reliable theoretical basis for the analysis of the flow field and the thermal fatigue analysis for the pipeline system with high completion of nuclear power and other structures.
【學(xué)位授予單位】：北京化工大學(xué)
【學(xué)位級(jí)別】：博士
【學(xué)位授予年份】：2017
【分類號(hào)】：TK124;TM623

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