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核電站反應(yīng)堆保護(hù)系統(tǒng)研究

發(fā)布時(shí)間:2018-02-02 22:10

  本文關(guān)鍵詞: 核電廠 反應(yīng)堆保護(hù)系統(tǒng) 可靠性 緊急停堆 專(zhuān)設(shè)安全設(shè)施 出處:《華北電力大學(xué)》2013年碩士論文 論文類(lèi)型:學(xué)位論文


【摘要】:反應(yīng)堆保護(hù)系統(tǒng)是核電站最重要系統(tǒng)之一,是反應(yīng)堆穩(wěn)定、可靠運(yùn)行的有力保障。因此,核電廠反應(yīng)堆保護(hù)系統(tǒng)對(duì)可靠性要求非常高。數(shù)字化的反應(yīng)堆保護(hù)系統(tǒng)是產(chǎn)生與保護(hù)任務(wù)有關(guān)的必要信息,防止反應(yīng)堆狀態(tài)超過(guò)規(guī)定的安全限值或減輕超過(guò)安全限值所造成的損壞和損失后果的安全系統(tǒng)。 當(dāng)反應(yīng)堆出現(xiàn)異常,但還不致馬上危及反應(yīng)堆安全時(shí),為確保電站連續(xù)運(yùn)行,反應(yīng)堆保護(hù)系統(tǒng)發(fā)出報(bào)警信號(hào)或由閉鎖系統(tǒng)提供校正措施,使反應(yīng)堆恢復(fù)到正常運(yùn)行狀態(tài);當(dāng)運(yùn)行保護(hù)參數(shù)超過(guò)了設(shè)計(jì)停堆整定值時(shí),能快速緊急停堆;當(dāng)出現(xiàn)超出停堆保護(hù)能力的事故時(shí),能啟動(dòng)相應(yīng)的專(zhuān)設(shè)安全設(shè)施,縮小事故范圍和防止放射性污染;當(dāng)電站運(yùn)行達(dá)到某種狀態(tài)時(shí),允許手動(dòng)或自動(dòng)閉鎖某些保護(hù)動(dòng)作,防止系統(tǒng)誤動(dòng)作。 核電廠數(shù)字化反應(yīng)堆保護(hù)系統(tǒng)較傳統(tǒng)基于模擬技術(shù)的反應(yīng)堆保護(hù)系統(tǒng)具有很多優(yōu)點(diǎn),是核電廠反應(yīng)堆保護(hù)系統(tǒng)發(fā)展的一個(gè)必然趨勢(shì)。本文通過(guò)研究國(guó)內(nèi)外反應(yīng)堆保護(hù)系統(tǒng)技術(shù)發(fā)展的現(xiàn)狀,調(diào)研了國(guó)內(nèi)外反應(yīng)堆保護(hù)系統(tǒng)相關(guān)技術(shù);通過(guò)對(duì)國(guó)內(nèi)外先進(jìn)技術(shù)消化吸收,逐步研究出具有我國(guó)自主知識(shí)產(chǎn)權(quán)的中國(guó)品牌的數(shù)字化的反應(yīng)堆保護(hù)技術(shù)。本文根據(jù)國(guó)內(nèi)外相關(guān)的法規(guī)標(biāo)準(zhǔn)、系統(tǒng)功能要求、設(shè)備設(shè)計(jì)要求,同時(shí)綜合考慮了與其他系統(tǒng)的接口,最終提出了以下設(shè)計(jì)方案:①進(jìn)行設(shè)計(jì)基準(zhǔn)分析,確定反應(yīng)堆保護(hù)系統(tǒng)設(shè)計(jì)滿足需要遵循的國(guó)際國(guó)內(nèi)法規(guī),,確保系統(tǒng)設(shè)計(jì)滿足核安全相關(guān)要求;②根據(jù)反應(yīng)堆堆工功能和安全性的需求,定義反應(yīng)堆保護(hù)系統(tǒng)的各種性能(安全等級(jí)、系統(tǒng)結(jié)構(gòu)、功能實(shí)現(xiàn)等);③對(duì)系統(tǒng)進(jìn)行可靠性分析,滿足單一故障準(zhǔn)則、冗余性和獨(dú)立性、多樣性、邏輯符合性準(zhǔn)則、故障安全準(zhǔn)則、可試驗(yàn)性和可維修性準(zhǔn)則。④根據(jù)現(xiàn)行的數(shù)字化技術(shù)和項(xiàng)目的堆型需要,確定反應(yīng)堆保護(hù)系統(tǒng)的結(jié)構(gòu)和實(shí)現(xiàn)方式。
[Abstract]:Reactor protection system is one of the most important nuclear power plant systems, is a stable and reliable operation of the reactor can ensure. Nuclear power plant reactor protection system requires very high reliability. Digital reactor protection system is necessary to generate information related to the protection mission. A safety system that prevents reactor status from exceeding the prescribed safety limit or mitigates damage and loss consequences caused by exceeding the safety limit. When the reactor is abnormal but does not immediately endanger the safety of the reactor, in order to ensure the continuous operation of the power station, the reactor protection system sends out an alarm signal or provides correction measures by the latch system. Return the reactor to normal operation; When the operation protection parameter exceeds the setting value of the design shutdown, the emergency shutdown can be achieved quickly. When there is an accident beyond the protection capacity of the reactor shutdown, the corresponding special safety facilities can be activated to reduce the scope of the accident and prevent radioactive contamination; When the power station is in a certain state, some protection actions are allowed to be closed manually or automatically to prevent system maloperation. Compared with the traditional reactor protection system based on analog technology, the digital reactor protection system of nuclear power plant has many advantages. It is an inevitable trend in the development of nuclear power plant reactor protection system. This paper investigates the relevant technologies of reactor protection system at home and abroad by studying the current situation of the development of reactor protection system technology at home and abroad. Through digesting and absorbing advanced technologies at home and abroad, the digital reactor protection technology of Chinese brands with independent intellectual property rights in China has been developed step by step. At the same time, the design requirements of the equipment and the interface with other systems are considered synthetically. Finally, the following design scheme: 1 is put forward to carry out the design benchmark analysis to determine that the design of the reactor protection system meets the international and domestic laws and regulations that need to be followed. Ensure that the system design meets the requirements related to nuclear safety; (2) according to the requirements of reactor reactor function and safety, define the performance of reactor protection system (safety grade, system structure, function realization and so on); The reliability analysis of the system satisfies the single fault criterion, redundancy and independence, diversity, logic conformance criterion and fault safety criterion. Test and maintainability guidelines .4 determine the structure and implementation of the reactor protection system according to the current digital technology and the reactor type requirements of the project.
【學(xué)位授予單位】:華北電力大學(xué)
【學(xué)位級(jí)別】:碩士
【學(xué)位授予年份】:2013
【分類(lèi)號(hào)】:TL364

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