【摘要】：第三代AP1000核電廠在嚴(yán)重事故下,堆芯鋯合金與高溫水蒸氣發(fā)生反應(yīng)生成氫氣。氫氣通過一回路壓力邊界破口進(jìn)入安全殼空間,氫氣燃燒或爆炸產(chǎn)生的熱及壓力載荷會威脅安全殼的完整性,導(dǎo)致放射性向環(huán)境和公眾泄漏。嚴(yán)重事故下,必須對氫氣進(jìn)行控制與管理,消除能導(dǎo)致安全殼失效的大體積氫氣燃爆。AP1000核電廠采用非能動氫氣復(fù)合器和點火器來降低氫氣風(fēng)險。 本文首先建立了AP1000核電廠MAAP程序模型,對于1#SG隔間內(nèi)冷管段小破口疊加ADS4失效事故的事故進(jìn)程進(jìn)行了研究,并計算得到了氫氣源項、水蒸氣源項、安全殼壓力和氣體溫度等參數(shù)。然后利用GASFLOW程序?qū)錃饩徑庀到y(tǒng)有效性進(jìn)行了CFD分析。研究表明：點火器能夠在氫氣大量釋放階段消耗掉大部分氫氣,而復(fù)合器對于大量氫氣集中釋放情況的緩解效果有限；非能動安全殼冷卻系統(tǒng)可以有效降低安全殼溫度和壓力；AP1000原有點火器方案可以有效降低上部空間的氫氣風(fēng)險,但1#SG隔間仍具有很高的氫氣風(fēng)險；通過在1#SG隔間添加兩臺氫氣點火器,在1#SG隔間上方添加1臺氫氣點火器,可明顯提升氫氣緩解系統(tǒng)性能,可控制1#SG隔間氫氣風(fēng)險,因此通過在氫氣富集區(qū)域合理加裝點火器可以有效控制該區(qū)域的氫氣風(fēng)險。 最后,本文分析了AP1000核電廠在小破口疊加ADS失效事故且點火器失效情況下惰化氣體注入時間和注入流量對于安全殼事故后惰化的影響。分析表明,過早開始惰化會導(dǎo)致較大的氫氣風(fēng)險,500s開始注射方案較優(yōu),惰化氣體的注入流量以23kg/s注射方案較優(yōu)。
[Abstract]:In the third generation AP1000 nuclear power plant, the core zirconium alloy reacts with high temperature steam to form hydrogen under serious accidents. Hydrogen enters the containment space through the pressure boundary break of the primary circuit. The heat and pressure load produced by hydrogen combustion or explosion will threaten the integrity of the containment and lead to the leakage of radioactivity to the environment and the public. In the case of serious accidents, hydrogen must be controlled and managed to eliminate the large volume hydrogen explosion which can lead to the failure of containment. AP1000 nuclear power plant uses passive hydrogen compounding device and igniter to reduce the risk of hydrogen. In this paper, the MAAP program model of AP1000 nuclear power plant is established, and the accident process of small break superposition ADS4 failure accident in 1#SG compartment is studied, and the hydrogen source term and water vapor source term are calculated. Containment pressure and gas temperature and other parameters. Then the CFD analysis of the effectiveness of hydrogen mitigation system is carried out by using GASFLOW program. The results show that the igniter can consume most of the hydrogen in the stage of hydrogen release, but the effect of the compound on the concentrated release of a large amount of hydrogen is limited, and the passive containment cooling system can effectively reduce the temperature and pressure of the containment. The original AP1000 igniter scheme can effectively reduce the hydrogen risk in the upper space, but the 1#SG compartment still has a high hydrogen risk. By adding two hydrogen igniters to the 1#SG compartment and one hydrogen igniter above the 1#SG compartment, the performance of the hydrogen mitigation system can be obviously improved, and the hydrogen risk in the 1#SG compartment can be controlled. Therefore, the hydrogen risk in this area can be effectively controlled by reasonably installing igniters in hydrogen enrichment area. Finally, the influence of inerting gas injection time and injection flow rate on inertia after containment accident in AP1000 nuclear power plant under the condition of small breakout superimposed ADS failure and igniter failure is analyzed in this paper. The analysis shows that the early start of inertia will lead to a greater risk of hydrogen, the 500s injection scheme is better, and the injection flow rate of inerting gas is better than that of 23kg/s injection scheme.
【學(xué)位授予單位】：華北電力大學(xué)
【學(xué)位級別】：碩士
【學(xué)位授予年份】：2014
【分類號】：TM623

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本文編號：2472988