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  本文關(guān)鍵詞： 大型先進(jìn)壓水堆 壓力容器 下筒體及下封頭 應(yīng)力評定 局部模型　出處：《首都經(jīng)濟(jì)貿(mào)易大學(xué)》2015年碩士論文　論文類型：學(xué)位論文

【摘要】：核能作為一種安全、經(jīng)濟(jì)、清潔和可持續(xù)發(fā)展的發(fā)電方式,已經(jīng)為社會所接受,核能發(fā)電也是我國能源戰(zhàn)略的組成部分之一,在能源供應(yīng)總量中的比例正在逐步提高。積極推進(jìn)核電建設(shè)是國家重要的能源戰(zhàn)略,對于滿足經(jīng)濟(jì)和社會發(fā)展不斷增長的能源需求,實(shí)現(xiàn)能源、經(jīng)濟(jì)和生態(tài)環(huán)境協(xié)調(diào)發(fā)展以及提升我國綜合經(jīng)濟(jì)實(shí)力和工業(yè)技術(shù)水平具有重要意義。反應(yīng)堆壓力容器是核電廠反應(yīng)堆冷卻劑壓力邊界屏障中的一個重要設(shè)備。它主要用來裝載反應(yīng)堆堆芯,密封高溫、高壓的冷卻劑,為反應(yīng)堆安全運(yùn)行提供所必需的堆芯控制和堆內(nèi)測量的導(dǎo)向和定位。反應(yīng)堆壓力容器屬安全一級設(shè)備,因此,要求其在各種工況下均能保持可靠的結(jié)構(gòu)完整性,不會發(fā)生容器的破壞和放射性的泄漏。筒體是壓力容器的主要部件,與封頭或管板共同構(gòu)成承壓殼體,為物料的儲存,完成介質(zhì)的物理、化學(xué)反應(yīng)及其他工藝用途提供所必需的承壓空間。下封頭是保證壓力容器密封的重要部件。因此,下筒體和下封頭的安全性是設(shè)計(jì)和使用中至關(guān)重要的問題,對它們進(jìn)行應(yīng)力評定是十分必要的。論文以大型先進(jìn)壓水堆核電廠壓力容器下筒體及下封頭為研究對象,根據(jù)ASME《鍋爐與壓力容器規(guī)范》中的相關(guān)要求,基于有限元方法,完成了反應(yīng)堆壓力容器下筒體及下封頭在各種工況各種載荷組合作用下的一次應(yīng)力強(qiáng)度的計(jì)算、分析與評定,并分析各個載荷對應(yīng)力分布的影響,最終得出了結(jié)構(gòu)強(qiáng)度符合規(guī)范要求的結(jié)論。在此基礎(chǔ)上,本文通過簡化整體模型,創(chuàng)建局部模型,對下筒體和下封頭作進(jìn)一步應(yīng)力評定,并將計(jì)算結(jié)果與整體模型的結(jié)果進(jìn)行對比分析。本論文的研究結(jié)果可為該壓力容器的設(shè)計(jì)提供技術(shù)支撐。
[Abstract]:Nuclear energy, as a safe, economic, clean and sustainable power generation method, has been accepted by the society, and nuclear power generation is also one of the components of our energy strategy. The proportion of total energy supply is gradually increasing. Actively promoting the construction of nuclear power is an important national energy strategy to meet the growing energy demand of economic and social development and to achieve energy. The coordinated development of economy and ecological environment and the improvement of China's comprehensive economic strength and industrial technological level are of great significance. Reactor pressure vessel is an important equipment in the reactor coolant pressure boundary barrier of nuclear power plant. Mainly used to load reactor cores. Sealed high temperature, high pressure coolant, for the safe operation of the reactor to provide the necessary core control and reactor measurement of guidance and positioning. Reactor pressure vessel is a safe first class equipment, therefore. It is required to maintain reliable structural integrity under various working conditions, without the vessel damage and radioactive leakage. The cylinder is the main component of pressure vessel, together with the head or pipe plate to form a pressure shell. Provides the necessary pressure space for the storage of materials, the completion of physical, chemical reaction and other technological uses of the medium. The lower head is an important component to ensure the sealing of the pressure vessel. The safety of the lower barrel and the lower head is an important problem in the design and use. It is very necessary to evaluate their stress. This paper takes the lower cylinder and lower head of pressure vessel of large advanced PWR nuclear power plant as the research object, according to the relevant requirements of ASME Code of Boiler and pressure vessel. Based on the finite element method, the calculation, analysis and evaluation of the primary stress intensity of the reactor pressure vessel under various load combinations are completed. The influence of each load on the stress distribution is analyzed, and finally the conclusion that the structural strength meets the requirements of the code is obtained. On the basis of this, the local model is created by simplifying the whole model. Further stress assessment is made for the lower cylinder and head, and the results of calculation are compared with those of the whole model. The research results in this paper can provide technical support for the design of the pressure vessel.
【學(xué)位授予單位】：首都經(jīng)濟(jì)貿(mào)易大學(xué)
【學(xué)位級別】：碩士
【學(xué)位授予年份】：2015
【分類號】：TM623.91;TL351.6

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本文編號：1473451