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Cycle Calculations of a Small-Scale Heat Removal System With Supercritical CO 2 as Working Fluid

机译:具有超临界CO 2 作为工作流体的小规模散热系统的循环计算

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摘要

In the case of an accident in a nuclear power plant with combined initiating events (loss of ultimate heat sink and station blackout), an additional heat removal system could transfer the decay heat from the core to an ultimate heat sink (UHS). One specific additional heat removal system, based upon a Brayton cycle with supercritical carbon dioxide (CO _( 2 ) ) as working fluid, is currently investigated within the European Union-funded project “sCO _( 2 ) -HeRo” (supercritical carbon dioxide heat removal system). It serves as a self-launching, self-propelling, and self-sustaining decay heat removal system used in severe accident scenarios. Since this Brayton cycle produces more electric power than it consumes, the excess electric power can be used inside the power plant, e.g., for recharging batteries. A small-scale demonstrator is attached to the pressurized water reactor (PWR) glass model at Gesellschaft für Simulatorschulung (GfS), Essen, Germany. In order to design and build this small-scale model, cycle calculations are performed to determine the design parameters from which a layout can be derived.
机译:在具有组合启动事件的核电厂发生事故的情况下(终极散热器和站停电的损失),额外的散热系统可以将衰变热从核心转移到终极散热器(UHS)。一种特定的额外散热系统,基于带有超临界二氧化碳(CO _(2))作为工作流体的Brayton循环,目前在欧盟资助的项目“SCO _(2)-ChO”(超临界二氧化碳中)进行研究散热系统)。它是在严重事故情景中使用的自动启动,自动推进和自我维持的衰变散热系统。由于该布雷顿循环产生比消耗更多的电力,因此可以在电厂内使用多余的电力,例如,用于充电电池。小型演示器附着在GesellschaftFürSimulatorschulung(GFS),埃森,德国的加压水反应堆(PWR)玻璃模型附加到加压水反应堆(PWR)玻璃模型。为了设计和构建该小规模模型,执行循环计算以确定可以导出布局的设计参数。

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