發(fā)布時(shí)間：2019-07-06 18:55

【摘要】：近年來(lái),隨著核技術(shù)的不斷發(fā)展,核技術(shù)在核能發(fā)電、工業(yè)、農(nóng)業(yè)以及醫(yī)學(xué)等領(lǐng)域均得到了廣泛應(yīng)用。與此同時(shí),核安全一直是為人們所關(guān)注的話題。為了提高核事故發(fā)生后的應(yīng)急能力,就需要研發(fā)出更多新型、高效的核輻射監(jiān)測(cè)設(shè)備。本課題組針對(duì)國(guó)內(nèi)外現(xiàn)有的幾種監(jiān)測(cè)方式所存在的一些不足,充分發(fā)揮本校航空航天特色學(xué)科的優(yōu)勢(shì),將傳統(tǒng)的核輻射監(jiān)測(cè)設(shè)備與小型無(wú)人旋翼機(jī)相結(jié)合,研發(fā)出了一套小型無(wú)人旋翼機(jī)機(jī)載輻射監(jiān)測(cè)系統(tǒng)。本文圍繞系統(tǒng)研發(fā)過(guò)程中所涉及的關(guān)鍵硬件電路設(shè)計(jì)、FPGA控制邏輯設(shè)計(jì)以及系統(tǒng)性能測(cè)試這幾方面的內(nèi)容展開(kāi)研究。(1)在制定系統(tǒng)的總體設(shè)計(jì)方案基礎(chǔ)上,按功能的不同,對(duì)系統(tǒng)進(jìn)行了模塊劃分,并利用Cadence軟件對(duì)其中的電源模塊、GM管劑量率模塊以及數(shù)據(jù)采集模塊等關(guān)鍵模塊進(jìn)行了原理圖及布局布線設(shè)計(jì)。在設(shè)計(jì)過(guò)程中,對(duì)電源紋波的控制、高壓電路的設(shè)計(jì)以及提高電路抗干擾能力等關(guān)鍵技術(shù)問(wèn)題進(jìn)行了較為詳細(xì)的研究,并給出了相應(yīng)的解決方法。測(cè)試結(jié)果顯示,硬件電路達(dá)到了設(shè)計(jì)要求。(2)介紹了基于FPGA的系統(tǒng)總體邏輯設(shè)計(jì),并將整個(gè)系統(tǒng)劃分為劑量率模塊、傳感器模塊以及串口通信模塊等多個(gè)功能模塊,逐個(gè)實(shí)現(xiàn)不同模塊的功能,對(duì)設(shè)計(jì)過(guò)程中的一些關(guān)鍵問(wèn)題進(jìn)行了探討。借助于ModelSim仿真軟件對(duì)完成的設(shè)計(jì)進(jìn)行了仿真,仿真測(cè)試結(jié)果顯示,模塊的控制邏輯正常。最后,PC端的調(diào)試界面顯示的結(jié)果表明,幾路數(shù)據(jù)均可被成功采集并發(fā)送至PC模塊。(3)闡述了系統(tǒng)劑量率模塊功能實(shí)現(xiàn)過(guò)程中所涉及的原理及方法,并對(duì)劑量率測(cè)量準(zhǔn)確度進(jìn)行了測(cè)試。對(duì)系統(tǒng)靈敏度測(cè)試必要性進(jìn)行了詳細(xì)討論,并采用了MCNP模擬與實(shí)驗(yàn)相結(jié)合的方法,最終得到了不同源條件下活度與最大可探測(cè)距離之間的函數(shù)關(guān)系。最后進(jìn)行了戶外實(shí)際飛行測(cè)試,測(cè)試了系統(tǒng)的整體性能狀況。各項(xiàng)測(cè)試結(jié)果表明,系統(tǒng)在劑量率測(cè)量、能譜測(cè)量和無(wú)線數(shù)據(jù)傳輸?shù)确矫娴墓δ芫?達(dá)到了系統(tǒng)的設(shè)計(jì)要求。本文的研究工作對(duì)整套監(jiān)測(cè)系統(tǒng)功能的實(shí)現(xiàn)具有重要意義。在本文研究工作的基礎(chǔ)上,結(jié)合相應(yīng)的算法,可以進(jìn)一步提升系統(tǒng)的性能。該監(jiān)測(cè)系統(tǒng)未來(lái)可用于日常的輻射環(huán)境監(jiān)測(cè)以及丟失放射源的搜尋。
文內(nèi)圖片：
圖片說(shuō)明：傳統(tǒng)的輻射監(jiān)測(cè)方式：(a)靜態(tài)監(jiān)測(cè)，(b)人工便攜式監(jiān)測(cè)，(c)車載式監(jiān)測(cè)，(d)機(jī)載式航空監(jiān)測(cè)
[Abstract]:In recent years, with the continuous development of nuclear technology, nuclear technology has been widely used in nuclear power generation, industry, agriculture, medicine and other fields. At the same time, nuclear safety has always been a topic of concern. In order to improve the emergency ability after nuclear accident, it is necessary to develop more new and efficient nuclear radiation monitoring equipment. In view of the shortcomings of several existing monitoring methods at home and abroad, our research group has given full play to the advantages of our university's aerospace characteristic disciplines, combined the traditional nuclear radiation monitoring equipment with the small unmanned rotor aircraft, and developed a set of airborne radiation monitoring system for the small unmanned rotor aircraft. In this paper, the key hardware circuit design, FPGA control logic design and system performance test involved in the system research and development process are studied. (1) on the basis of making the overall design scheme of the system, according to the different functions of the system, the module of the system is divided, and the power supply module is divided by Cadence software. The schematic diagram and layout and wiring of GM tube dose rate module and data acquisition module are designed. In the process of design, the key technical problems, such as the control of power supply ripples, the design of high voltage circuit and the improvement of anti-interference ability of the circuit, are studied in detail, and the corresponding solutions are given. The test results show that the hardware circuit meets the design requirements. (2) the overall logic design of the system based on FPGA is introduced, and the whole system is divided into dose rate module, sensor module and serial communication module. The functions of different modules are realized one by one, and some key problems in the design process are discussed. With the help of ModelSim simulation software, the design is simulated. The simulation test results show that the control logic of the module is normal. Finally, the results of PC debugging interface show that several data can be successfully collected and sent to PC module. (3) the principle and method involved in the realization of the function of system dose rate module are described, and the accuracy of dose rate measurement is tested. The necessity of sensitivity test of the system is discussed in detail, and the method of combining MCNP simulation with experiment is adopted. Finally, the functional relationship between activity and maximum recoverable distance under different source conditions is obtained. Finally, the outdoor flight test is carried out, and the overall performance of the system is tested. The test results show that the function of the system in dose rate measurement, energy spectrum measurement and wireless data transmission is normal, which meets the design requirements of the system. The research work of this paper is of great significance to the realization of the whole monitoring system. On the basis of the research work of this paper, combined with the corresponding algorithm, the performance of the system can be further improved. The monitoring system can be used for daily radiation environment monitoring and the search for lost radioactive sources in the future.
【學(xué)位授予單位】：南京航空航天大學(xué)
【學(xué)位級(jí)別】：碩士
【學(xué)位授予年份】：2017
【分類號(hào)】：TL751

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