AP1000核电厂安全壳内氢气风险缓解措施研究
发布时间：2019-05-09 18:31
【摘要】：第三代AP1000核电厂在严重事故下,堆芯锆合金与高温水蒸气发生反应生成氢气。氢气通过一回路压力边界破口进入安全壳空间,氢气燃烧或爆炸产生的热及压力载荷会威胁安全壳的完整性,导致放射性向环境和公众泄漏。严重事故下,必须对氢气进行控制与管理,消除能导致安全壳失效的大体积氢气燃爆。AP1000核电厂采用非能动氢气复合器和点火器来降低氢气风险。 本文首先建立了AP1000核电厂MAAP程序模型,对于1#SG隔间内冷管段小破口叠加ADS4失效事故的事故进程进行了研究,并计算得到了氢气源项、水蒸气源项、安全壳压力和气体温度等参数。然后利用GASFLOW程序对氢气缓解系统有效性进行了CFD分析。研究表明：点火器能够在氢气大量释放阶段消耗掉大部分氢气,而复合器对于大量氢气集中释放情况的缓解效果有限；非能动安全壳冷却系统可以有效降低安全壳温度和压力；AP1000原有点火器方案可以有效降低上部空间的氢气风险,但1#SG隔间仍具有很高的氢气风险；通过在1#SG隔间添加两台氢气点火器,在1#SG隔间上方添加1台氢气点火器,可明显提升氢气缓解系统性能,可控制1#SG隔间氢气风险,因此通过在氢气富集区域合理加装点火器可以有效控制该区域的氢气风险。 最后,本文分析了AP1000核电厂在小破口叠加ADS失效事故且点火器失效情况下惰化气体注入时间和注入流量对于安全壳事故后惰化的影响。分析表明,过早开始惰化会导致较大的氢气风险,500s开始注射方案较优,惰化气体的注入流量以23kg/s注射方案较优。
[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.
【学位授予单位】：华北电力大学
【学位级别】：硕士
【学位授予年份】：2014
【分类号】：TM623
本文编号：2472988
[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.
【学位授予单位】：华北电力大学
【学位级别】：硕士
【学位授予年份】：2014
【分类号】：TM623
【参考文献】
中国期刊全文数据库 前2条
1 肖建军;周志伟;经荥清;;湍流模型对安全壳内氢气浓度场模拟的影响[J];原子能科学技术;2006年06期
2 林千;周全福;;AP1000核电厂氢气点火器功能分析[J];原子能科学技术;2012年01期
，本文编号：2472988
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