【摘要】：隨著核電的發(fā)展，核電站的安全問(wèn)題日益受到人們的關(guān)注。從幾次大型的災(zāi)難性事故中可以看出，核電站的抗震能力需進(jìn)一步研究。而核安全殼結(jié)構(gòu)是核電站安全的最后一道屏障，因此對(duì)其進(jìn)行抗震研究具有重大意義。 本文基于某核安全殼1:15的縮比模型，進(jìn)行了振動(dòng)臺(tái)抗震試驗(yàn)與隔震試驗(yàn)，，并采用ANSYS對(duì)該安全殼分別進(jìn)行普通結(jié)構(gòu)和隔震結(jié)構(gòu)的抗震有限元分析。從結(jié)果進(jìn)行對(duì)比研究中，評(píng)估了地震作用下核安全殼普通結(jié)構(gòu)與隔震結(jié)構(gòu)的抗震性能。 首先根據(jù)相似比理論，設(shè)計(jì)制作了某核安全殼結(jié)構(gòu)1:15縮尺模型，并對(duì)模型施加配重，建立安全殼結(jié)構(gòu)的欠人工質(zhì)量傳統(tǒng)抗震模型，利用量綱分析法推導(dǎo)出了試驗(yàn)?zāi)Ｐ退裱南嗨茰?zhǔn)則及各物理量的相似比。根據(jù)相應(yīng)規(guī)范選取并調(diào)整符合實(shí)際場(chǎng)地條件的地震波，進(jìn)行在峰值為0.1g、0.2g、0.3g地震波作用下的安全殼普通結(jié)構(gòu)的地震振動(dòng)臺(tái)試驗(yàn)，記錄給出了關(guān)鍵部位的加速度、位移、應(yīng)變響應(yīng)數(shù)據(jù)。接著，應(yīng)用MATLAB軟件對(duì)試驗(yàn)數(shù)據(jù)進(jìn)行分析，得出安全殼抗震模型的動(dòng)力特性和動(dòng)力響應(yīng)規(guī)律。 在安全殼結(jié)構(gòu)縮尺模型基礎(chǔ)上，選取天然橡膠墊作為安全殼結(jié)構(gòu)的隔震層，建立安全殼結(jié)構(gòu)的隔震模型。根據(jù)模型的參數(shù)數(shù)據(jù)，對(duì)隔震層進(jìn)行豎向承載力和水平側(cè)移的驗(yàn)算，保證隔震層參數(shù)滿(mǎn)足試驗(yàn)要求。然后，按照傳統(tǒng)抗震模型地震波的選取原則和調(diào)整方法進(jìn)行地震波的選取與調(diào)整，進(jìn)行峰值為0.152g、0.304g、0.608g地震波作用下安全殼隔震振動(dòng)臺(tái)試驗(yàn)。在對(duì)動(dòng)力試驗(yàn)響應(yīng)數(shù)據(jù)進(jìn)行分析的基礎(chǔ)上，給出安全殼隔震模型的動(dòng)力特性和動(dòng)力響應(yīng)規(guī)律。 最后，在ANSYS中建立整體式鋼筋混凝土安全殼傳統(tǒng)抗震以及隔震有限元模型，系統(tǒng)考慮安全殼結(jié)構(gòu)的邊界條件和配重等影響因素，以試驗(yàn)測(cè)得臺(tái)面加速度作為地震波輸入，分別進(jìn)行了傳統(tǒng)抗震模型、隔震模型的模態(tài)分析以及時(shí)程響應(yīng)分析。并對(duì)試驗(yàn)分析和數(shù)值模擬的結(jié)果進(jìn)行對(duì)比分析，綜合評(píng)估安全殼結(jié)構(gòu)的抗震和隔震性能。 通過(guò)研究表明，安全殼結(jié)構(gòu)傳統(tǒng)抗震模型具有較大剛度，對(duì)輸入地震波具有放大效果，但幅度不明顯，表明安全殼傳統(tǒng)抗震模型具有良好的抗震能力。安全殼隔震模型能夠有效限制地震力向上部結(jié)構(gòu)傳遞，減小上部結(jié)構(gòu)的地震響應(yīng)；安全殼結(jié)構(gòu)整體呈現(xiàn)為剛體平動(dòng)，側(cè)向位移較大，主要產(chǎn)生在隔震層。本文對(duì)于安全殼結(jié)構(gòu)抗震與隔震性能對(duì)比研究，可為核電站安全殼結(jié)構(gòu)抗震性能分析提供參考。
[Abstract]:With the development of nuclear power, people pay more and more attention to the safety of nuclear power plants. It can be seen from several catastrophic accidents that the seismic capacity of nuclear power plants needs further study. The nuclear safety shell structure is the last barrier of nuclear power plant safety, so it is of great significance to study the earthquake resistance of nuclear power plant. Based on the 1:15 shrinkage model of a nuclear safety shell, the seismic test and isolation test of shaking table are carried out, and the seismic finite element analysis of the ordinary structure and isolated structure is carried out by ANSYS. In this paper, the seismic performance of the normal structure and isolated structure of nuclear safety shell under earthquake action is evaluated by comparing the results. Based on the similarity ratio theory, the 1:15 scale model of a nuclear safety shell structure is designed and made, and the traditional seismic model of the containment structure with less artificial quality is established by applying counterweight to the model. By means of dimensional analysis, the similarity criterion and the similarity ratio of each physical quantity are derived. According to the corresponding specifications, the seismic waves which accord with the actual site conditions are selected and adjusted, and the seismic shaking table test of the common containment structure with a peak value of 0.1 g / 0.2g / 0.3g seismic wave is carried out. The acceleration and displacement of the key parts are recorded. Strain response data. Then, the test data are analyzed by MATLAB software, and the dynamic characteristics and dynamic response of the containment seismic model are obtained. Based on the scale model of containment structure, natural rubber cushion is selected as the isolation layer of containment structure, and the isolation model of containment structure is established. According to the parameter data of the model, the vertical bearing capacity and horizontal lateral displacement of the isolation layer are checked to ensure that the parameters of the isolation layer meet the test requirements. Then, according to the selection principle and adjustment method of traditional seismic model seismic wave, the vibration table test of containment isolation under the action of 0.152g / 0.304g / 0.608g seismic wave is carried out. Based on the analysis of dynamic test response data, the dynamic characteristics and dynamic response of containment isolation model are presented. Finally, the traditional seismic and isolation finite element models of integral reinforced concrete containment are established in ANSYS. The influence factors such as boundary condition and counterweight of containment structure are systematically considered, and the measured Mesa acceleration is used as the seismic wave input. The modal analysis of the traditional seismic model and the isolated model is carried out to analyze the response in time. The results of experimental analysis and numerical simulation are compared to evaluate the seismic and isolation performance of containment structures. The results show that the traditional seismic model of containment structure has large stiffness and magnification effect on the input seismic wave, but the amplitude is not obvious, which indicates that the traditional seismic model of containment structure has good seismic capacity. Containment isolation model can effectively limit the transfer of seismic force to the upper structure and reduce the seismic response of the upper structure. This paper provides a reference for seismic performance analysis of containment structures in nuclear power plants.
【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】：2013
【分類(lèi)號(hào)】：TL364.3;TU352.11

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