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Experimental investigation on condensation heat transfer for bundle tube heat exchanger of the PCCS (Passive Containment Cooling System)

机译:PCCS(被动安全壳冷却系统)束管式热交换器冷凝水传热的实验研究

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To provide a passive cooling system for the reactor containment. Passive Containment Cooling System (PCCS) was adopted in the design of i-POWER nuclear power plant. This study focused on validation tests for condensation heat transfer of the PCCS heat exchanger using the CLASSIC facility. The tests include investigation of the condensation heat transfer in prototypic single tube and bundle tubes. From the single tube experiments, condensation heat transfer model was proposed to reflect the PCCS heat exchanger tube geometry. Experimental results in the bundle tube show consistent trend compared to the proposed heat transfer model from the single tube test. The local condensation heat transfer coefficient of inside tubes was smaller than the average value due to a shadow effect by a larger mass fraction of non-condensable gas, so that design of the PCCS should take into account degradation of the condensation heat removal in the bundle geometry. (C) 2019 Elsevier Ltd. All rights reserved.
机译:为反应堆安全壳提供被动冷却系统。 i-POWER核电站的设计采用了被动安全壳冷却系统(PCCS)。这项研究的重点是使用CLASSIC设备进行的PCCS热交换器冷凝水传热的验证测试。测试包括调查原型单管和束管中的冷凝热传递。通过单管实验,提出了冷凝传热模型来反映PCCS换热器管的几何形状。与单管测试中提出的传热模型相比,束管中的实验结果显示出一致的趋势。内管的局部冷凝传热系数由于较大的不可冷凝气体质量分数的阴影效应而小于平均值,因此PCCS的设计应考虑束中冷凝散热量的降低。几何。 (C)2019 Elsevier Ltd.保留所有权利。

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