核电站运行过程中反应性变化的分析

J. Sierchuła
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引用次数: 2

摘要

2017年,全球共有449座核反应堆在运行发电。压水堆占所有反应堆的60%以上。这种类型的最现代化的反应堆之一是由西屋公司开发的AP1000反应堆。由于经济和技术原因以及安全系统的原因,上述建设也考虑到波兰第一座核电站的建设,这一建设已经非常广泛和实施。本文在介绍核电站技术体系的同时,介绍了AP1000反应堆的模型。除其他外,上述模型允许研究燃料组件位置对有效中子增殖因子/反应性的影响。此外,研究了慢化剂与中子能量之间的关系(中子通量密度作为能量的函数确定),并给出了正常运行时反应堆堆芯产生的裂变生成量。为了验证所建立的模型,对所得结果进行了分析,并参考了文献数据。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Analysis of reactivity changes during the operation of a nuclear power plant
In 2017, 449 nuclear reactors were operating for electricity generation in the world. More than 60% of all reactors were represented by pressurized water reactors. One of the most modern reactors of this type is the AP1000 reactor, developed by Westinghouse. The mentioned construction is also taken into account in terms of the construction of the first nuclear power plant in Poland, for both economic and technical reasons as well as safety systems, which have been very extensive and implemented in this construction. In the following paper, apart from the presentation of the nuclear power plant technology system, model of AP1000 reactor was presented. Above mentioned model allows, among other things, to investigate the influence of fuel assemblies locations on the effective neutron multiplication factor/reactivity. In addition, the relation between moderator and neutrons energy was examined (the neutron flux density was determined as a function of energy) and the amount of fission products generated in the reactor core during normal operation was presented. The obtained results were analysed and referenced to the literature data in order to verify the created model.
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