Abstract 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.

中文翻译：

---

PCCS（Passive Containment Cooling System）束管式换热器冷凝传热实验研究

摘要 为了给反应堆安全壳提供被动冷却系统，i-POWER核电站设计采用了被动安全壳冷却系统（PCCS）。本研究侧重于使用 CLASSIC 设施对 PCCS 换热器的冷凝传热进行验证测试。测试包括研究原型单管和束管中的冷凝传热。从单管实验中，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。由于较大质量分数的不凝气体的阴影效应，管内局部冷凝传热系数小于平均值，