管壳式换热器-传热面积设计过程

Q3 Engineering
Štefan Gužela, František Dzianik, Martin Juriga, Juraj Kabát
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引用次数: 9

摘要

摘要如今,运行中的核反应堆只能利用开采出来的1%的铀。在所谓的快堆中,可以实现铀的有效开采,甚至60%。这些反应堆预计将在2035年后投入商业运行。这些反应器有几种设计配置。快堆属于所谓的第四代反应堆。氦冷堆作为一种气冷快堆,就是其中之一。用于从反应堆活性区传热的换热器(即换热器)是快堆的重要组成部分。本文讨论了U型管换热器(精确到1-2个带U型管的管壳式换热器):水-氦的设计计算。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Shell and Tube Heat Exchanger – the Heat Transfer Area Design Process
Abstract Nowadays, the operating nuclear reactors are able to utilise only 1 % of mined out uranium. An effective exploitation of uranium, even 60 %, is possible to achieve in so-called fast reactors. These reactors commercial operation is expected after the year 2035. Several design configurations of these reactors exist. Fast reactors rank among the so-called Generation IV reactors. Helium-cooled reactor, as a gas-cooled fast reactor, is one of them. Exchangers used to a heat transfer from a reactor active zone (i.e. heat exchangers) are an important part of fast reactors. This paper deals with the design calculation of U-tube heat exchanger (precisely 1-2 shell and tube heat exchanger with U-tubes): water – helium.
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来源期刊
Strojnicky Casopis
Strojnicky Casopis Engineering-Mechanical Engineering
CiteScore
2.00
自引率
0.00%
发文量
33
审稿时长
14 weeks
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