發(fā)布時(shí)間：2018-07-01 12:43

  本文選題：加速器驅(qū)動(dòng)次臨界系統(tǒng) + 鉛鉍冷卻反應(yīng)堆��； 參考：《深圳大學(xué)》2015年碩士論文

【摘要】：加速驅(qū)動(dòng)次臨界系統(tǒng)是一種新型的核廢料嬗變、核燃料增殖及能量生產(chǎn)的核能系統(tǒng)。該系統(tǒng)主要由質(zhì)子加速器、散裂靶和次臨界堆組成,利用加速器產(chǎn)生的質(zhì)子轟擊重金屬散裂靶產(chǎn)生的散裂中子驅(qū)動(dòng)反應(yīng)堆中的核燃料發(fā)生核反應(yīng),實(shí)現(xiàn)嬗變處理核廢料、增殖核燃料、生產(chǎn)能量等功能。鉛鉍合金具有良好的中子學(xué)、熱工水力學(xué)和安全特性,鉛鉍冷卻反應(yīng)堆被選作中國加速驅(qū)動(dòng)次臨界堆的主要發(fā)展方向。中國科學(xué)院核能安全技術(shù)研究所?FDS團(tuán)隊(duì)完成了加速器驅(qū)動(dòng)次臨界鉛鉍冷卻反應(yīng)堆的概念設(shè)計(jì)。反應(yīng)堆的物項(xiàng)(構(gòu)筑物、系統(tǒng)和部件)對反應(yīng)堆的安全影響程度不同,因此需要根據(jù)物項(xiàng)對反應(yīng)堆安全重要影響程度的不同將物項(xiàng)進(jìn)行分類,這就是反應(yīng)堆的安全分級。反應(yīng)堆物項(xiàng)安全等級的正確劃分是各項(xiàng)管理要求和規(guī)定的基礎(chǔ)。正確劃分鉛鉍冷卻反應(yīng)堆安全等級是選擇和采用合適的抗震水平、設(shè)計(jì)規(guī)范和質(zhì)量保證等級的前提。因此,在鉛鉍冷卻反應(yīng)堆的設(shè)計(jì)階段,就必須對鉛鉍冷卻反應(yīng)堆物項(xiàng)進(jìn)行安全等級的劃分。目前,國際上還沒有公布針對鉛鉍冷卻反應(yīng)堆物項(xiàng)安全分級的規(guī)范和導(dǎo)則。本論文以鉛鉍冷卻反應(yīng)堆為研究對象進(jìn)行安全分級方法的初步研究。首先,調(diào)研了國內(nèi)外針對壓水堆、沸水堆的確定論安全分級方法和risk-informed的安全分級方法;其次,根據(jù)上述確定論安全分級方法的一般流程,采用主邏輯圖法推導(dǎo)出適用于鉛鉍冷卻反應(yīng)堆的安全功能,然后對安全功能進(jìn)行安全等級的劃分,最后確定出安全功能適用的物項(xiàng),這就是針對鉛鉍冷卻反應(yīng)堆的確定論安全分級方法;再次,根據(jù)鉛鉍冷卻反應(yīng)堆的特點(diǎn)提出了針對鉛鉍冷卻反應(yīng)堆的risk-informed的安全分級方法體系;最后分別運(yùn)用以上兩種方法對鉛鉍冷卻反應(yīng)堆的冷卻劑系統(tǒng)和鉛鉍工藝系統(tǒng)進(jìn)行實(shí)例分級研究。通過上述兩種方法的對比分析可以得出,risk-informed安全分級適用范圍有限,但risk-informed安全分級比確定論安全分級更加詳細(xì)和合理。未來主要工作可以考慮放在對鉛鉍冷卻反應(yīng)堆其它系統(tǒng)的確定論安全分級和risk-informed的安全分級上,并通過分級結(jié)果進(jìn)一1步完善上述兩種安全分級方法。
[Abstract]:Accelerated drive subcritical system is a new nuclear energy system for nuclear waste transmutation, nuclear fuel proliferation and energy production. The system is mainly composed of proton accelerator, spallation target and subcritical reactor. The nuclear fuel in the reactor driven by spallation neutron driven by heavy metal spallation target is bombarded by the proton produced by the accelerator to realize the transmutation treatment of nuclear waste. Proliferation of nuclear fuel, production of energy and other functions. Lead bismuth alloy has good neutron, thermal hydraulics and safety properties. Lead bismuth cooling reactor is selected as the main development direction of accelerating drive subcritical reactor in China. The FDS team of the Institute of Nuclear Safety Technology of the Chinese Academy of Sciences has completed the conceptual design of a subcritical lead bismuth cooled reactor driven by an accelerator. Reactor items (structures, systems and components) have different effects on reactor safety, so it is necessary to classify items according to their importance to reactor safety, which is called reactor safety classification. The correct classification of reactor item safety level is the basis of all management requirements and regulations. Correctly dividing the safety grade of lead bismuth cooling reactor is the premise of selecting and adopting appropriate seismic level, design code and quality assurance grade. Therefore, in the design stage of lead bismuth cooling reactor, the safety grade of lead bismuth cooling reactor must be classified. At present, there are no international standards and guidelines for the safety classification of lead-bismuth cooling reactor items. In this thesis, lead-bismuth cooling reactor is studied as the primary method of safety classification. Firstly, the safety classification method of PWR and boiling water reactor and the safety classification method of risk-informed are investigated; secondly, the general process of safety classification method based on the above determination theory is discussed. The safety function suitable for lead bismuth cooling reactor is deduced by using the main logic diagram method. Then the safety function is classified and the items applicable to the safety function are determined. This is the safety classification method for lead bismuth cooled reactor. Thirdly, according to the characteristics of lead bismuth cooling reactor, the safety classification method system for lead bismuth cooled reactor risk-informed is put forward. Finally, the coolant system and lead-bismuth process system of lead bismuth cooling reactor are studied by the two methods mentioned above. Through the comparison and analysis of the above two methods, it can be concluded that the application range of risk-formed security classification is limited, but the risk-informed security classification is more detailed and reasonable than the deterministic theory of security classification. In the future, the main work can be considered on the safety classification of other systems of lead bismuth cooling reactor and the safety classification of risk-informed, and the two safety classification methods mentioned above can be improved one step further through the result of the classification.
【學(xué)位授予單位】：深圳大學(xué)
【學(xué)位級別】：碩士
【學(xué)位授予年份】：2015
【分類號】：TL364

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