This article is devoted to model calculations of a lead-cooled reactor core performed using the EVKLID/V1 code. The ingress of water vapor into the core is modeled for the stationary state of the reactor at the rated power capacity. The change in the reactivity and power at different mass flow of water vapor is analyzed. Baseline calculations performed using the MCU-FR code were performed in order to substantiate the correctness of the EVKLID/V1 neutron-physical characteristics when experimental data are lacking.

中文翻译：

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水蒸气进入冷却剂的铅冷反应堆堆芯的 EVKLID/V1 建模

本文专门讨论使用 EVKLID/V1 代码执行的铅冷反应堆堆芯的模型计算。水蒸气进入堆芯的模拟是针对反应堆在额定功率容量下的静止状态。分析了不同质量水蒸气流量下反应性和功率的变化。使用 MCU-FR 代码执行的基线计算是为了在缺乏实验数据时证实 EVKLID/V1 中子物理特性的正确性。