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首页> 外文期刊>Polish maritime research >Comparison Analysis of Selected Nuclear Power Plants Supplied With Helium from High-Temperature Gas-Cooled Reactor
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Comparison Analysis of Selected Nuclear Power Plants Supplied With Helium from High-Temperature Gas-Cooled Reactor

机译：高温气冷反应器供应选定核电站的比较分析

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The article presents results of efficiency calculations for two 560 MW nuclear cycles with high-temperature gas-cooled reactor (HTGR). An assumption was made that systems of this type can be used in so-called marine nuclear power plants. The first analysed system is the nuclear steam power plant. For the steam cycle, the efficiency calculations were performed with the code DIAGAR, which is dedicated for analysing this type of systems. The other system is the power plant with gas turbine, in which the combustion chamber has been replaced with the HTGR. For this system, a number of calculations were also performed to assess its efficiency. Moreover, the article names factors in favour of floating nuclear power plants with HTGRs, which, due to passive safety systems, are exposed to much smaller risk of breakdown than other types of reactors which were in common use in the past. Along with safety aspects, it is also economic and social aspect which make the use of this type of systems advisable.
机译：本文介绍了具有高温气体冷却反应器（HTGR）的两种560 MW核循环的效率计算结果。假设这种类型的系统可用于所谓的海洋核电厂。第一个分析的系统是核蒸汽发电厂。对于蒸汽循环，使用代码既迪亚加进行效率计算，专门用于分析这种类型的系统。另一个系统是具有燃气轮机的发电厂，其中燃烧室已被HTGR替换。对于该系统，还进行了许多计算来评估其效率。此外，文章名称因素有利于HTGRS浮动核电厂，由于被动安全系统，由于过去的其他类型的反应器暴露于比其他类型的反应器更小的崩溃风险。随着安全方面，它也是经济和社会方面，这是利用这种类型的系统可取的。

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