Abstract

Russian systems of intermediate separation and superheating of steam, operated as part of steam turbines of all nuclear power plants, operate with an insufficient level of reliability and efficiency. Design temperatures of overheating steam are not reached in most cases. The paper analyzes the characteristics of the working processes occurring in the apparatus: the flow of superheated wet steam in the separator and the superheater stages, dehumidification and subsequent flow of the separation in the separators, the intensity of heat exchange between the condensing heating steam of high pressure and the heated steam of low pressure, as well as the condensate flow of heating steam. Proposals are formulated to create more reliable and efficient devices, taking into account half a century of domestic and international experience in their design and operation.

中文翻译：

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通过基于物理模型的现代化升级，对带有压水和沸水反应堆的核电站中的过热器进行升级

摘要

作为所有核电厂蒸汽轮机一部分运行的俄罗斯蒸汽中间分离和过热系统，其可靠性和效率水平不足。在大多数情况下，不会达到过热蒸汽的设计温度。本文分析了该设备中发生的工作过程的特征：分离器和过热器阶段中的过热湿蒸汽流，分离器中除湿和分离后的分离流，冷凝的加热蒸汽之间的热交换强度。高压和低压加热的蒸汽，以及加热蒸汽的冷凝水。制定了旨在创建更可靠，更高效的设备的提案，