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首页> 外文期刊>Bulletin of the Institute of Heat Engineering >Efficiency of selected methods of hydrogen removal from a nuclear reactor’s containment building
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Efficiency of selected methods of hydrogen removal from a nuclear reactor’s containment building

机译:从核反应堆安全壳中脱氢的精选方法的效率

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The system of barriers is utilized to prevent a release of radioactive materials to the environment from a nuclear reactor's core. These barriers are the nuclear fuel structure, fuel cladding, walls of the primary cooling circuit and the containment building. Reliability of these barriers is very high and it is very unlikely to fail them all simultaneously. A one of crucial issues for containment integrity is the problem of hydrogen combustion and detonation. Gaseous hydrogen may be released into the containment building from overheated core region either during a loss-of-coolant accident by a break in the primary cooling circuit, or by a safety relieve valve (as in Fukushima Dai-ichi nuclear power plant). Mixing of hydrogen with the air in the internal atmosphere creates flammable mixtures. Taking this into account it is very important to avoid such situations and make possible removal of this gas. Five methods of hydrogen removal from the containment building can be distinguished: - intended ignition of hydrogen for its controlled combustion, - recombination of hydrogen by catalytic devices, - removal of oxygen by pre-inertisation, - dilution of the atmosphere by post-accidental injection of inert gas, - dilution of the atmosphere by increase of the containment volume. Efficiency of these methods has been assessed based on results of simulations realized by means of the in-door computer code HEPCAL. This is the lumped parameter code for analysis of a nuclear reactor containment transient response. Real systems utilizing the described hydrogen removal methods have been simulated in the first step applying design basis accident scenarios. As the results could not be directly compared, in the second step a virtual experiment has been simulated too.
机译:屏障系统用于防止放射性物质从核反应堆堆芯释放到环境中。这些障碍是核燃料结构,燃料包壳,主冷却回路的壁和安全壳建筑。这些障碍的可靠性很高,不可能同时使它们全部失效。密闭完整性的关键问题之一是氢燃烧和爆炸的问题。气态氢可能会在一次冷却剂损失事故中由于一次冷却回路的中断或通过安全泄压阀(如在福岛第一核电站中)从过热的堆芯区域释放到安全壳建筑物中。氢气与内部大气中的空气混合会产生易燃混合物。考虑到这一点,避免这种情况并去除这种气体非常重要。从安全壳中去除氢的五种方法可以区分出来:-氢的有意燃烧以控制燃烧;-通过催化装置将氢重组;-通过预惰性化除去氧;-通过事后注入稀释大气惰性气体-通过增加安全壳体积来稀释大气。这些方法的效率已基于通过室内计算机代码HEPCAL实现的模拟结果进行了评估。这是用于分析核反应堆安全壳瞬态响应的集中参数代码。在第一步中,已经应用设计基准事故场景模拟了利用所述除氢方法的实际系统。由于无法直接比较结果,因此在第二步中也模拟了虚拟实验。

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