Abstract The operation of the nuclear reactor requires accurate and fast methods and techniques for analysing its kinetics. These techniques become even more important when the MOX-fuel is used due to the lower value of delayed neutron fraction β for 239Pu. Based on a Birth-and-Death process review, the mathematical model of thermal reactor core has been proposed different from existing ones. The analytical method for thermal point-reactor parameters evaluation is described within this work. The proposed method is applied for analysis of the unsteady transient processes taking place in a thermal reactor at its start-up or shutdown power change, as well as during small accidental power variation from the rated value. Theoretical determination of MASURCA reactor core reactivity through the analysis of experimental data on neutron time spectra was made.

中文翻译：

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使用生死模型对使用 MOX 燃料的亚临界反应堆堆芯进行瞬态分析

摘要 核反应堆的运行需要准确、快速的方法和技术来分析其动力学。当使用 MOX 燃料时，这些技术变得更加重要，因为 239Pu 的延迟中子分数 β 值较低。在回顾生死过程的基础上，提出了不同于现有模型的热堆堆芯数学模型。在这项工作中描述了热点反应器参数评估的分析方法。所提出的方法用于分析热反应堆在启动或关闭功率变化时以及在与额定值的小的偶然功率变化期间发生的非稳态瞬态过程。