Autonomous Thermosiphon System of Passive Residual Heat Removal from the Primary Circuit of the Reactor Plant: Features of Operation, Characteristics and Basic Advantages

Q3 Energy
I. I Sviridenko, D. V. Shevelyov
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Abstract

An autonomous system of passive removal of residual heat (PRRHS) of a reactor installation with VVER designed to ensure the safety of nuclear power plants in an accident with complete long-term blackout is considered. The system provides for the removal of heat directly from the first circuit of the reactor plant (PRRHS R). In order to increase the reliability and safety of the emergency heat sink, heat exchange equipment based on closed-type evaporation and condensation devices – two-phase thermosyphons – has been used in the system. The main feature of such heat exchangers is that their thermosiphon assemblies structurally separate the primary circuit and the auxiliary circuit of the PRRHS, which is removed outside the reactor compartment, and provide safe and efficient heat removal, reduce the risk of radioactive contamination spreading beyond safety barriers. Such autonomous passive systems will provide effective heat removal directly from the primary circuit by changing the chain of successive heat transfer sites from nuclear fuel to the final absorber and excluding from it such elements, as for example steam generators, the condition and operability of which in the emergency process of heat removal have a major impact on the safety of the reactor core. The article presents a diagram of an autonomous heat sink system; also, a description of its operation is given. The main characteristics of the course of the emergency process of removal of residual heat by the autonomous thermosiphon PRRHS R obtained by computational modeling have been considered. The advantages of an autonomous thermosiphon passive system in comparison with a passive heat removal system of a reactor installation with VVER through the second circuit are analyzed. The obtained results are proposed to solve the problems of diversification of passive safety systems of evolutionary reactor plants of nuclear power plants with VVER type reactors.
反应堆装置一次回路被动余热自动热虹吸系统:运行特点、特点及基本优势
为保证核电站在完全长期停电事故下的安全,研究了VVER反应堆装置的自主被动余热排出系统。该系统提供直接从反应堆装置第一回路(PRRHS R)排出热量。为了提高应急散热器的可靠性和安全性,系统中采用了基于闭式蒸发冷凝装置的换热设备——两相热虹吸。这种热交换器的主要特点是其热虹吸组件在结构上将PRRHS的主回路和辅助回路分开,并将其移出反应堆室外,并提供安全有效的散热,降低放射性污染扩散到安全屏障之外的风险。这种自主被动系统将通过改变从核燃料到最终吸收体的连续传热点链,并排除蒸汽发生器等元件,直接从初级回路提供有效的热量排出,这些元件在紧急排热过程中的状况和可操作性对反应堆堆芯的安全有重大影响。本文给出了一种自主散热系统的框图;并对其操作进行了描述。考虑了通过计算模型得到的自主热虹吸应急除余热过程的主要特点。分析了自主热虹吸被动排热系统与二次回路VVER被动排热系统的优越性。所得结果可用于解决VVER型反应堆核电站演化堆装置被动安全系统的多样化问题。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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来源期刊
CiteScore
1.60
自引率
0.00%
发文量
32
审稿时长
8 weeks
期刊介绍: The most important objectives of the journal are the generalization of scientific and practical achievements in the field of power engineering, increase scientific and practical skills as researchers and industry representatives. Scientific concept publications include the publication of a modern national and international research and achievements in areas such as general energetic, electricity, thermal energy, construction, environmental issues energy, energy economy, etc. The journal publishes the results of basic research and the advanced achievements of practices aimed at improving the efficiency of the functioning of the energy sector, reduction of losses in electricity and heat networks, improving the reliability of electrical protection systems, the stability of the energetic complex, literature reviews on a wide range of energy issues.
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