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Time-fractional telegraph equation for hydrogen diffusion during severe accident in BWRs

机译:压水堆严重事故中氢扩散的时间分数电报方程

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The aim of this work is to study the behavior of heat and mass transfer during hydrogen generation in the core of the boiling water reactor (BWR). The core of the BWR is a system highly heterogeneous where the transport processes are complex. The core is considered as an average channel of the fuel assembly, which consists of arrays of in-line fuel rod. This study considers diffusion and reaction due to generation of hydrogen during severe accident in a nuclear power plant with reactor type BWR. The temperature distribution in the nuclear fuel is obtained with a normal diffusion model, whereas that of the distribution of the hydrogen concentration is obtained with a time-fractional telegraph equation (TFTE). The TFTE allows consider the anomalous diffusion processes (non-Fickian effects), which govern the transport in heterogeneous systems. The numerical experiments were performance in an averaging channel that represents a core reactor with the fuel rod with its gap and cladding and cooling steam, in order to establish the importance of the effects of hydrogen diffusion in a severe accident scenario. The initial conditions of this scenario correspond to 100% of rated power, with scram of the reactor, and without cooling flow. The temperature of the fuel is incremented due to decay heat, and due to lack of cooling the fuel temperature increases, which eventually causes fuel cladding oxidation and hydrogen generation. The hydrogen concentration results in a reaction due to oxidation for different values of fractional coefficient, at t = 0 and short times were obtained. The physical meaning is discussed when the fractional coefficient tends to a value of 1 and when it tends to a value of 0.5, i.e., within the limits of validity of the fractional model proposed. According to the results obtained the hydrogen concentration is inversely proportional to the fractional coefficient. These results are relevant for decision making in terms of risk analysis in nuclear power plant with BWR.
机译:这项工作的目的是研究沸水反应堆(BWR)堆芯中制氢过程中的传热和传质行为。 BWR的核心是高度异构的系统,其中的传输过程非常复杂。堆芯被认为是燃料组件的平均通道,该通道由成排的燃料棒阵列组成。这项研究考虑了在反应堆类型为BWR的核电厂发生严重事故期间由于氢的产生而引起的扩散和反应。核燃料中的温度分布是通过正态扩散模型获得的,而氢浓度分布的温度分布是通过时间分数电报方程(TFTE)获得的。 TFTE可以考虑控制异质系统中传输的异常扩散过程(非菲克效应)。数值实验是在一个平均通道中进行的,该通道代表一个带有堆芯和堆层以及冷却蒸汽的燃料棒的堆芯反应堆,以便确定在严重事故情况下氢扩散效应的重要性。这种情况的初始条件对应于100%的额定功率,带有反应堆,没有冷却流。燃料的温度由于衰变热而升高,并且由于缺乏冷却而使燃料温度升高,这最终导致燃料包壳氧化和氢气产生。对于不同的分数系数值,在t = 0时,氢浓度导致由于氧化而发生的反应,并获得了短时间。当分数系数趋向于1且趋于于0.5时,即在所提出的分数模型的有效性范围内,讨论了物理意义。根据获得的结果,氢浓度与分数系数成反比。这些结果与具有BWR的核电厂进行风险分析方面的决策有关。

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